Removal of radium from drinking water

International Nuclear Information System (INIS)

Lauch, R.P.

1992-08-01

The report summarizes processes for removal of radium from drinking water. Ion exchange, including strong acid and weak acid resin, is discussed. Both processes remove better than 95 percent of the radium from the water. Weak acid ion exchange does not add sodium to the water. Calcium cation exchange removes radium and can be used when hardness removal is not necessary. Iron removal processes are discussed in relation to radium removal. Iron oxides remove much less than 20 percent of the radium from water under typical conditions. Manganese dioxide removes radium from water when competition for sorption sites and clogging of sites is reduced. Filter sand that is rinsed daily with dilute acid will remove radium from water. Manganese dioxide coated filter sorption removes radium but more capacity would be desirable. The radium selective complexer selectively removes radium with significant capacity if iron fouling is eliminated

Plasma spraying of beryllium and beryllium-aluminum-silver alloys

International Nuclear Information System (INIS)

Castro, R.G.; Stanek, P.W.; Elliott, K.E.; Jacobson, L.A.

1994-01-01

A preliminary investigation on plasma-spraying of beryllium and a beryllium-aluminum-4% silver alloy was done at the Los Alamos National Laboratory's Beryllium Atomization and Thermal Spray Facility (BATSF). Spherical Be and Be-Al-4%Ag powders, which were produced by centrifugal atomization, were used as feedstock material for plasma-spraying. The spherical morphology of the powders allowed for better feeding of fine (<38 μm) powders into the plasma-spray torch. The difference in the as-deposited densities and deposit efficiencies of the two plasma-sprayed powders will be discussed along with the effect of processing parameters on the as-deposited microstructure of the Be-Al-4%Ag. This investigation represents ongoing research to develop and characterize plasma-spraying of beryllium and beryllium-aluminum alloys for magnetic fusion and aerospace applications

Plasma spraying of beryllium and beryllium-aluminum-silver alloys

International Nuclear Information System (INIS)

Castro, R.G.; Stanek, P.W.; Elliott, K.E.; Jacobson, L.A.

1993-01-01

A preliminary investigation on plasma-spraying of beryllium and a beryllium-aluminum 4% silver alloy was done at the Los Alamos National Laboratory's Beryllium Atomization and Thermal Spray Facility (BATSF). Spherical Be and Be-Al-4%Ag powders, which were produced by centrifugal atomization, were used as feedstock material for plasma-spraying. The spherical morphology of the powders allowed for better feeding of fine (<38 μm) powders into the plasma-spray torch. The difference in the as-deposited densities and deposit efficiencies of the two plasma-sprayed powders will be discussed along with the effect of processing parameters on the as-deposited microstructure of the Be-Al-4%Ag. This investigation represents ongoing research to develop and characterize plasma-spraying of beryllium and beryllium-aluminum alloys for magnetic fusion and aerospace applications

Travel report on a preparatory mission to the Agencija RAO, Ljubljana for a radium conditioning operation

International Nuclear Information System (INIS)

Neubauer, J.

2001-07-01

The purpose of the trip was to establish the current status of radioactive waste management in Slovenia, to discuss their plans for the future management of their radioactive wastes and to prepare for a radium source conditioning operation to make safe and secure their known inventory of radium withdrawn from service. The IAEA are considering placing a contract on the Oesterreichisches Forschungszentrum Seibersdorf (OeFZS) to carry out the radium conditioning operation on the agency's behalf in a manner used successfully on a number of previous occasions. In Slovenia responsibility for the management of radioactive wastes arising from nuclear applications in medicine research and industry is delegated to 'Agencija Rao'. First a visit was made to the storage building in which such wastes are stored, the building being within the grounds of the Josef Stefan Institute in Ljubljana. The possibility of carrying out the radium conditioning operation in the building and the improvements and modifications necessary was discussed. The inventory of stored waste was reviewed, the packages containing radium were identified and located in the store. Some of these contained radium-beryllium sources. It was agreed that such sources would not be conditioned during the forthcoming operation. Next a visit was made to the chemistry laboratories of the Josef Stefan Institute, these being a possible alternative location for the operation. On returning to the 'Agencija Rao' office in Ljubljana detail discussion of the merits of the alternative locations were discussed. It was realized that the operation could proceed quicker and at less cost if the existing laboratory was chosen, the unknown factor is the time taken to obtain regulatory approval. Next detailed discussion took place of the availability of necessary equipment and consumable items and agreement reached on what should be supplied locally and what should be brought to Slovenia, by the conditioning team. Plans were made to

Personal characteristics relating to radium loss over a decade or more in radium dial workers

International Nuclear Information System (INIS)

Stebbings, J.H.; Jansen, A.; Kotek, T.J.

1986-01-01

Personal habits and biological characteristics of 42 female Illinois radium workers first employed during the 1920s were analyzed in relationship to radium loss in late adult life. The 42 women met the criteria that they first were examined between 1957 and 1969 and are no longer employed, have had two or more radium body-burden measurements by gamma spectroscopy, 10-year minimum interval exists between initial and final measurements, and exhibit a RaC body burden in 1970 or later of ≥.137 kBQ. High radium body burdens are associated with decreased rates of radium elimination, as previously described. However, the most powerful predictor was coffee/tea consumption, increased consumption being associated with increased rates of radium elimination and explaining ∼35% of the variance. The effect persisted after deletion of smokers and subjects with x-ray evidence of bone damage. Weight/height ratios were positively associated with radium excretion. Individuals smoking cigarettes throughout the study period had significantly low rates of elimination of radium, similar to subjects with x-ray evidence of significant radiation-induced bone damage. Both smokers and subjects with x-ray evidence of radiation damage to bone had low weight/height ratios, suggesting that biological promoters of radiation damage to bone may exist. Rates of radium elimination were significantly associated with (linear) bone density, demonstrating that rates of loss of radium cannot be assumed to be independent of adult or postmenopausal bone density losses. Number of children and age of menopause did not have demonstrable effects on radium elimination. 9 refs., 2 figs., 7 tabs

Personal characteristics relating to radium loss over a decade or more in radium dial workers

International Nuclear Information System (INIS)

Stebbings, J.H.; Kotek, T.J.; Jansen, A.

1987-01-01

Personal habits and biological characteristics of 42 female Illinois radium workers first employed during the 1920s were analyzed in relationship to radium loss in late adult life. The 42 women met the following criteria: (1) first examined between 1957 and 1969, and no longer employed; (2) two or more radium body-burden measurements by gamma spectroscopy; (3) 10-year minimum interval between initial and final measurements; and (4) a RaC body burden in 1970 or later of ≥0.137 kBq. High radium body burdens were significantly associated with decreased rates of radium elimination; however, the most powerful predictor was coffee/tea consumption (p<.005), increased consumption being associated with increased rates of radium elimination and explaining ∼35% of the variance. The effect persisted after deletion of smokers and subjects with X-ray evidence of bone damage. Weight/height ratios were positively associated with radium excretion (p<.025). Smokers throughout the study period had significantly low rates of elimination of radium, similar to subjects with X-ray evidence of significant radiation-induced bone damage. Both smokers and subjects with X-ray evidence of radiation damage to bone had low weight/height ratios, suggesting that biological promoters of radiation damage to bone may exist. Rates of radium elimination were significantly associated with bone density, demonstrating that rates of loss of radium cannot be assumed to be independent of adult or postmenopausal bone density losses. Parity and age of menopause did not demonstrably affect radium elimination. 7 refs.; 2 figs.; 7 tabs

Biological effects of radium

International Nuclear Information System (INIS)

Drosselmeyer, E.

1982-12-01

It is evident from a survey of the current literature that a problem exists in finding the correlation between the exposure of the human body to radiation, with the subsequent development of diseases, particularly for certain types of cancer. A brief history of the early experiences of radium incorporation into humans is given followed by data collected on some important polulation groups exposed to radium body burden, such as miners in rare metal and uranium mines, dial painters and some groups of patients. The medical and technical applications of radium are discussed. A summary is also given of the natural occurence of radium and the amounts in which it is present in the environment. Incorporation, retention and excretion pathways are outlined. In order to study the metabolism and the induction of diseases by radium several animal studies have been performed. The ICRP regards radium-226 as the best known and most studied radionuclide. It can thus serve as a guideline for setting limits for other radionuclides, e.g. plutonium. The valid limiting value for radium-226 of 0.1 μCi for whole body exposure is generally accepted and regarded as sufficiently safe. Finally, transfer factors have been collected as fas as they were available in the literature. (orig./MG) [de

Beryllium

International Nuclear Information System (INIS)

Hansen, N.B.

1980-01-01

A method for determination of beryllium in minerals and rocks is described. The method comprises microanalysis and trace analysis. Because of the toxidity of beryllium the method is designed for determination of a hitherto unknown small amount, 1-10 nanogram Be. With the optimal amount for determination, 3 ng Be, the relative error of the method is 10%. The description includes an inventory of chemicals and apparatus, also an example of application of the method on the mineral epididymite. In brief, the sample is melted with sodium carbonate and sodium tetra borate; when required the sample in advance is fumed with hydrogen fluoride and sulphuric acid to evaporate silica. The residuum is dissolved in water and hydrogen chloride, upon which the solution is made to volume. In the Ring oven interfering compounds are masked with EDTA. Beryllium is settled with chrome azurol and ammonia. Beryllium is identified and evaluated in comparison with previously produced standards. (author)

Beryllium

International Nuclear Information System (INIS)

Hansen, N.B.

1979-01-01

A method for determination of beryllium in minerals and rocks is described. The method comprises microanalysis and trace analysis. Because of the toxidity of beryllium the method is designed for determination of a hitherto unknown small amount, 1-10 nanogram Be. With the optimal amount for determination, 3 ng Be, the relative error of the method is 10%. The description includes an inventory of chemicals and apparatus, also an example of application of the method on the mineral epididymite. In brief, the sample is melted with sodium carbonate and sodium tetra borate; when required the sample in advance is fumed with hydrogen fluoride and sulphuric acid to evaporate silica. The residuum is dissolved in water and hydrogen chloride, upon which the solution is made to volume. In the Ring oven interfering compounds are masked with EDTA. Beryllium is settled with chrome azurol and ammonia. Beryllium is identified and evaluated in comparison with previously produced standards. (author)

Beryllium health effects in the era of the beryllium lymphocyte proliferation test.

Science.gov (United States)

Maier, L A

2001-05-01

The beryllium lymphocyte proliferation test (BeLPT) has revolutionized our approach to the diagnosis, screening, and surveillance of beryllium health effects. Based on the development of a beryllium-specific cell-mediated immune response, the BeLPT has allowed us to define early health effects of beryllium, including beryllium sensitization (BeS), and chronic beryllium disease (CBD) at a subclinical stage. The use of this test as a screening tool has improved our understanding of these health effects. From a number of studies it is apparent that BeS precedes CBD and develops after as little as 9 weeks of beryllium exposure. CBD occurs within 3 months and up to 30 years after initial beryllium exposure. Exposure-response variables have been associated with BeS/CBD, including work as a machinist, chemical or metallurgical operator, laboratory technician, work in ceramics or beryllium metal production, and years of beryllium exposure. Recent studies have found BeS and CBD in workplaces in which the majority of exposures were below the 2 microg/m3 OSHA time-weighted average (TWA). Ideally, the BeLPT would be used in surveillance aimed at defining other risk-related processes, determining exposure variables which predict BeS and CBD, and defining the exposure level below which beryllium health effects do not occur. Unfortunately, the BeLPT can result in false negative tests and still requires an invasive procedure, a bronchoscopy, for the definitive diagnosis of CBD. Thus, research is needed to establish new tests to be used alone or in conjunction with the BeLPT to improve our ability to detect early beryllium health effects.

Corrosion of beryllium

International Nuclear Information System (INIS)

Mueller, J.J.; Adolphson, D.R.

1987-01-01

The corrosion behavior of beryllium in aqueous and elevated-temperature oxidizing environments has been extensively studied for early-intended use of beryllium in nuclear reactors and in jet and rocket propulsion systems. Since that time, beryllium has been used as a structural material in les corrosive environments. Its primary applications include gyro systems, mirror and reentry vehicle structures, and aircraft brakes. Only a small amount of information has been published that is directly related to the evaluation of beryllium for service in the less severe or normal atmospheric environments associated with these applications. Despite the lack of published data on the corrosion of beryllium in atmospheric environments, much can be deduced about its corrosion behavior from studies of aqueous corrosion and the experiences of fabricators and users in applying, handling, processing, storing, and shipping beryllium components. The methods of corrosion protection implemented to resist water and high-temperature gaseous environments provide useful information on methods that can be applied to protect beryllium for service in future long-term structural applications

Radium

International Nuclear Information System (INIS)

Cerskov-Klika, Midana; Lokner, Vladimir

1999-01-01

This paper describes the problem of control and/or storage of radiation sources used in hospitals in Croatia. The administration organization of the country, now being established; work on the new legislation, and the regulatory framework for protection against radiation, combined with a desire to achieve the systematic and safe storage of all existing radioactive waste, until the construction of a disposal site for low- and medium - level radiation waste, have all contributed to the decision whereby all radiation sources in Croatia are to be located and made safe. Accordingly, it was agreed that a commission, involving Croatian Health Ministry, the Hazardous Waste Management Agency, the Institute for Medical Research, and the Ruder Boskovic Institute, should organize the search, collection and conditioning of all radium sources which have been used in medical establishments throughout Croatia. The subsequent investigation revealed that almost half of all radium sources are located in an old storage facility at the Institute for Medical Research. Those sources, as well as others located in hospitals following months of investigation, have now been collected together in one place - the Ruder Boskovic Institute. Following a process of identification, and entry in a relevant data base, all sources were subject to a conditioning procedure. They were placed in stainless-steel capsules, each capsule containing approximately 50 milli curries of radium. The capsules are scaled with a lid, welded in a place using a special procedure, which totally isolates the contents from the environment. Neither radium nor its products are able to escape from the capsule. Then, the capsules, in groups of ten, are placed in a massive lead container, which prevents leakage of radiation resulting from disintegration. The lead container is placed inside a stainless-steel barrel filled with concrete. In this way, the radium sources no longer pose any threat to the environment. Due to its long

Radium dial workers

International Nuclear Information System (INIS)

Rowland, R.E.; Lucas, H.F. Jr.

1982-01-01

The population of radium dial workers who were exposed to radium 30 to 50 years ago are currently being followed by the Center for Human Radiobiology at the Argonne National Laboratory. It is not clear that radium has induced additional malignancies in this population, other than the well-known bone sarcomas and head carcinomas, but elevated incidence rates for multiple myeloma and cancers of the colon, rectum, stomach, and breast suggest that radium might be involved. Continued follow-up of this population may resolve these questions. Finally, the question of the effect of fetal irradiation on the offspring of these women remains to be resolved. No evidence exists to suggest that any effects have occurred, but there is no question that a chronic irradiation of the developing fetus did take place. No formal follow-up of these children has yet been initiated

Laser fabrication of beryllium components

International Nuclear Information System (INIS)

Hanafee, J.E.; Ramos, T.J.

1995-08-01

Working with the beryllium industry on commercial applications and using prototype parts, the authors have found that the use of lasers provides a high-speed, low-cost method of cutting beryllium metal, beryllium alloys, and beryllium-beryllium oxide composites. In addition, they have developed laser welding processes for commercial structural grades of beryllium that do not need a filler metal; i.e., autogenous welds were made in commercial structural grades of beryllium by using lasers

Beryllium and growth. III. The effect of beryllium on plant phosphatase

Energy Technology Data Exchange (ETDEWEB)

Hoagland, M B

1952-01-01

The purpose of the investigations was to correlate the apparent ability of beryllium to substitute for magnesium in plant growth with a specific biochemical effect of the metal. Through association with earlier work on beryllium inhibition of animal alkaline phosphatase, a study was made of the effect of beryllium and other metals upon the activity of a phosphatase derived from tomato leaves. Although only indirect evidence is available that this enzyme system was magnesium-activated, beryllium was found to inhibit reversibly the splitting of GP and ATP. Other metals were also found to be inhibitory but the ATP-ase inhibition - and especially the ratio of P split from GP to P split from ATP - was higher for beryllium than for any other metal studied. The significance of this finding in relation to energy metabolism, growth, and beryllium toxicity is discussed. 12 references, 5 figures, 2 tables.

Beryllium chemistry and processing

CERN Document Server

Walsh, Kenneth A

2009-01-01

This book introduces beryllium; its history, its chemical, mechanical, and physical properties including nuclear properties. The 29 chapters include the mineralogy of beryllium and the preferred global sources of ore bodies. The identification and specifics of the industrial metallurgical processes used to form oxide from the ore and then metal from the oxide are thoroughly described. The special features of beryllium chemistry are introduced, including analytical chemical practices. Beryllium compounds of industrial interest are identified and discussed. Alloying, casting, powder processing, forming, metal removal, joining and other manufacturing processes are covered. The effect of composition and process on the mechanical and physical properties of beryllium alloys assists the reader in material selection. The physical metallurgy chapter brings conformity between chemical and physical metallurgical processing of beryllium, metal, alloys, and compounds. The environmental degradation of beryllium and its all...

Eye changes induced by radium

International Nuclear Information System (INIS)

Taylor, G.N.; Lloyd, R.D.; Shabestari, L.; Angus, W.; Muggenburg, B.A.

1989-01-01

Radium-induced intraocular neoplasia has not been reported in people, nor were the intraocular pigmentary changes observed in the beagles described in the dial painters or the radium 226 iatrogenic cases. However, Spiess (1969) has observed a 25% incidence of multiple pigmented naevi in the iris of the radium 224 German cases and Stefani, Spiess and Mays (1986) have noted an abnormal incidence of cataracts in this same group of patients. The reasons for the absence of the much less severe radium-induced eye changes in man as compared to the dog has not been determined. Reference is also made to the authors radium 226 rodent studies with mouse strain onychomys leucogaster. (author)

Beryllium. Beryllium oxide, obtention and properties. Pt.4

International Nuclear Information System (INIS)

Lires, O.A.; Delfino, C.A.; Botbol, J.

1991-01-01

As a continuation of the 'Beryllium' series this work reviews several methods of high purity beryllia production. Diverse methods of obtention and purification from different beryllium compounds are described. Some chemical, mechanical and electrical properties related with beryllia obtention methods are summarized. (Author) [es

Denver radium site's - Case history

International Nuclear Information System (INIS)

Topolski, T.T.

1985-01-01

In developing this case history of the Denver radium sites, an attempt is made to establish the Colorado carnotite connection from the point of discovery to early development and its eventual role in the inception of the National Radium Institute and Denver's radium legacy. Early exploitive mining activities and the exportation of the highest grades of uranium ore to Europe greatly disturbed key officials at the U.S. Bureau of Mines. With its proximity to known carnotite deposits and industrial capacity, Denver's destiny as one of America's early radium production centers became a reality by 1914. With African pitchblend discoveries, Belgium competition spelled the beginning of the end of Denver's romance with radium by 1920. The sites where Denver made or used its radium were lost in obscurity for 60 years and rediscovered in 1979. Thirty one sites and a characterization of their radioactive impact are now a part of the Superfund National Priorities listing for eventual cleanup

Beryllium

International Nuclear Information System (INIS)

1988-01-01

In this data sheet the occurrence, ore processing, chemical and physical properties and the uses of beryllium and its alloys is presented. The hazards involved in the use of beryllium and its compounds in the laboratory are discussed with particular reference to its toxicity, carcinogenicity, handling, storage, disposal, fire prevention and the principal health hazards. Further reading is suggested. (UK)

Removal of radium from aqueous sulphate solutions

International Nuclear Information System (INIS)

Weir, D.R.; Masters, J.T.; Neven, M.

1983-01-01

Radium is often present in ores and an aqueous solution associated with the ore may consequently contain dissolved radium. It is frequently necessary to remove radium from such solutions to reduce the total radium content to a prescribed low level before the solution can be returned to the environment. The present invention is based on the discovery that the total radium content can be reduced to a satisfactory level within a reasonable time by adding a soluble barium salt to a radium-containing sulphate solution which also contains dissolved magnesium at a pH not greater than about 0 to precipitate radium as barium radium sulphate, raising the pH to at least 11 to precipitate an insoluble magnesium compound which collects the barium radium sulphate precipitate, and separating substantially all of the precipitates from the solution

Mechanisms of hydrogen retention in metallic beryllium and beryllium oxide and properties of ion-induced beryllium nitride; Rueckhaltemechanismen fuer Wasserstoff in metallischem Beryllium und Berylliumoxid sowie Eigenschaften von ioneninduziertem Berylliumnitrid

Energy Technology Data Exchange (ETDEWEB)

Oberkofler, Martin

2011-09-22

In the framework of this thesis laboratory experiments on atomically clean beryllium surfaces were performed. They aim at a basic understanding of the mechanisms occurring upon interaction of a fusion plasma with a beryllium first wall. The retention and the temperature dependent release of implanted deuterium ions are investigated. An atomistic description is developed through simulations and through the comparison with calculations based on density functional theory. The results of these investigations are compared to the behaviour of hydrogen upon implantation into thermally grown beryllium oxide layers. Furthermore, beryllium nitride is produced by implantation of nitrogen into metallic beryllium and its properties are investigated. The results are interpreted with regard to the use of beryllium in a fusion reactor. (orig.)

Radium removal from Canadian uranium mining effluents by a radium-selective ion exchange complexer

International Nuclear Information System (INIS)

1984-07-01

A laboratory test program was initiated by the Department of Energy, Mines and Resources as part of the National Uranium Tailings Program to investigate the applicability of a radium-selective ion exchange complexer for removing radium from Canadian uranium mining effluents. The ion exchange complexer was shown to be efficient in removing radium from contaminated water of uranium mining operations, with the ultimate loading capacity of the resin on one type of water treated being determined as approximately 1,600 Bq/cm 3 of new resin. The results showed that the resin was effective in removing radium but not any other contaminants

Extractive metallurgy of the beryllium

International Nuclear Information System (INIS)

Alonso, Neusa; Capocchi, Jose Deodoro Trani

1995-01-01

A bibliographic review is performed on the beryllium extractive metallurgy. The work describes the main type of ores and processes applied to the metallic beryllium production, beryllium oxide production using fluoride, sulfide and direct chlorination. The thermodynamic consideration are made on beryllium reduction processes, discussing the viability of the beryllium oxide and hallide reduction processes. Under the technological viewpoint, the Cu-Be alloys main production processes are discussed, and the main toxicity problems related with beryllium are mentioned

Proton irradiation effects on beryllium – A macroscopic assessment

Energy Technology Data Exchange (ETDEWEB)

Simos, Nikolaos, E-mail: simos@bnl.gov [Nuclear Sciences & Technology Department, Brookhaven National Laboratory, Upton, NY, 11973 (United States); Elbakhshwan, Mohamed [Nuclear Sciences & Technology Department, Brookhaven National Laboratory, Upton, NY, 11973 (United States); Zhong, Zhong [Photon Sciences, NSLS II, Brookhaven National Laboratory, Upton, NY, 11973 (United States); Camino, Fernando [Center for Functional Nanomaterials, Brookhaven National Laboratory, Upton, NY, 11973 (United States)

2016-10-15

Beryllium, due to its excellent neutron multiplication and moderation properties, in conjunction with its good thermal properties, is under consideration for use as plasma facing material in fusion reactors and as a very effective neutron reflector in fission reactors. While it is characterized by unique combination of structural, chemical, atomic number, and neutron absorption cross section it suffers, however, from irradiation generated transmutation gases such as helium and tritium which exhibit low solubility leading to supersaturation of the Be matrix and tend to precipitate into bubbles that coalesce and induce swelling and embrittlement thus degrading the metal and limiting its lifetime. Utilization of beryllium as a pion production low-Z target in high power proton accelerators has been sought both for its low Z and good thermal properties in an effort to mitigate thermos-mechanical shock that is expected to be induced under the multi-MW power demand. To assess irradiation-induced changes in the thermal and mechanical properties of Beryllium, a study focusing on proton irradiation damage effects has been undertaken using 200 MeV protons from the Brookhaven National Laboratory Linac and followed by a multi-faceted post-irradiation analysis that included the thermal and volumetric stability of irradiated beryllium, the stress-strain behavior and its ductility loss as a function of proton fluence and the effects of proton irradiation on the microstructure using synchrotron X-ray diffraction. The mimicking of high temperature irradiation of Beryllium via high temperature annealing schemes has been conducted as part of the post-irradiation study. This paper focuses on the thermal stability and mechanical property changes of the proton irradiated beryllium and presents results of the macroscopic property changes of Beryllium deduced from thermal and mechanical tests.

Exposure data for radium patients

International Nuclear Information System (INIS)

Anon.

1982-01-01

This appendix summarizes exposure data collected as of 31 December 1981 for 2282 radium cases under study at the Center for Human Radiobiology. It includes all persons meaasured for radium since the start of te Center in 1969 and all persons for whom we have analytic data from earlier work at the Radioactivity Center of the Massachusetts Institute of Technology, the New Jersey Radium Research Project of the New Jersey department of Health, and the Argonne Radium Studies at the Argonne National Laboratory and the Argonne Cancer Research Hospital

The centenary of discovery of radium

International Nuclear Information System (INIS)

Mazeron, J.-J.; Gerbaulet, A.

1998-01-01

Henri Becquerel presented the discovery of radium by Pierre and Marie Curie at the Paris Academy of Science on 26th December 1898. One century later, radium has been abandoned, mainly for radiation protection difficulties. It is, however, likely that modern techniques of brachytherapy have inherited to those designed for radium sources, and that radium has cured thousands and thousands patients all over the world for about eighty years. The history of discovery and medical use of radium is summarised. (Copyright (c) 1998 Elsevier Science B.V., Amsterdam. All rights reserved.)

Technical Basis for PNNL Beryllium Inventory

Energy Technology Data Exchange (ETDEWEB)

Johnson, Michelle Lynn

2014-07-09

The Department of Energy (DOE) issued Title 10 of the Code of Federal Regulations Part 850, “Chronic Beryllium Disease Prevention Program” (the Beryllium Rule) in 1999 and required full compliance by no later than January 7, 2002. The Beryllium Rule requires the development of a baseline beryllium inventory of the locations of beryllium operations and other locations of potential beryllium contamination at DOE facilities. The baseline beryllium inventory is also required to identify workers exposed or potentially exposed to beryllium at those locations. Prior to DOE issuing 10 CFR 850, Pacific Northwest Nuclear Laboratory (PNNL) had documented the beryllium characterization and worker exposure potential for multiple facilities in compliance with DOE’s 1997 Notice 440.1, “Interim Chronic Beryllium Disease.” After DOE’s issuance of 10 CFR 850, PNNL developed an implementation plan to be compliant by 2002. In 2014, an internal self-assessment (ITS #E-00748) of PNNL’s Chronic Beryllium Disease Prevention Program (CBDPP) identified several deficiencies. One deficiency is that the technical basis for establishing the baseline beryllium inventory when the Beryllium Rule was implemented was either not documented or not retrievable. In addition, the beryllium inventory itself had not been adequately documented and maintained since PNNL established its own CBDPP, separate from Hanford Site’s program. This document reconstructs PNNL’s baseline beryllium inventory as it would have existed when it achieved compliance with the Beryllium Rule in 2001 and provides the technical basis for the baseline beryllium inventory.

Removal of radium from drinking water

International Nuclear Information System (INIS)

Clifford, D.A.

1990-01-01

The traditional, proven process for radium removal are sodium ion exchange softening, lime softening, and reverse osmosis. The newer, radium-specific column processes include adsorption onto the Dow RSC and BaSO 4 -impregnated alumina. The most promising new radium-specific treatment process for large-scale use is adsorption onto preformed manganese dioxide followed by multimedia or diatomaceous earth filtration The disposal of radium-contaminated wastewaters and sludges from processes under consideration will be a major factor in process selection. The processes of choice for municipal water supply treatment to remove radium are sodium ion exchange softening, lime softening, manganese dioxide adsorption-filtration, and selective adsorption onto the Dow RSC or BaSO 4 -impregnated alumina. Where the water is brackish, reverse osmosis hyperfiltration should also be considered. The radium removal process of choice for whole-house or point-of-entry treatment is sodium ion exchange softening. For point-of-use radium removal, a standard reverse osmosis system including cartridge filtration, activated carbon adsorption, and reverse osmosis hyperfiltration is recommended. Although no cost estimates have been made, the relative costs from most expensive to least expansive, for radium removal in small community water supplies are reverse osmosis, sodium ion exchange softening, lime soda softening, manganese dioxide adsorption-filtration, and the radium-selective adsorbents. 34 refs., 7 figs., 2 tabs

Spectrographic measurement of beryllium in the atmosphere; Dosage spectrographique du beryllium dans l'atmosphere

Energy Technology Data Exchange (ETDEWEB)

Artaud, J; Cittanova, J [Commissariat a l' Energie Atomique, Service d' Analyses et Recherches Chimiques Appliquees, Saclay (France). Centre d' Etudes Nucleaires; Crehange, G; Frequelin, S [Commissariat a l' Energie Atomique, Dir. des Applications Militaires, Service Chimie, Saclay (France). Centre d' Etudes Nucleaires; Baudin, G [Commissariat a l' Energie Atomique, Grenoble (France). Centre d' Etudes Nucleaires

1961-07-01

We describe here a method for the spectrographic determination of beryllium on filters which is valid for amounts varying between 0,01 and 30 {mu}g of beryllium and which is independent of the nature of the beryllium compound involved. This is a flux method (graphite-lithium carbonate mixture), the excitation being by a direct current arc. (author) [French] Nous decrivons ici, une methode de dosage spectrographique de beryllium sur filtre, valable pour des teneurs comprises entre 0,01 et 30 {mu}g de beryllium et independante de la nature du compose de beryllium a doser. C'est une methode de 'flux' (melange graphite-carbonate de lithium) l'excitation etant un arc a courant continu. (auteur)

Determination of radium in water

International Nuclear Information System (INIS)

Hohorst, F.A.; Huntley, M.W.; Hartenstein, S.D.

1995-10-01

These detailed work instructions (DWIs) are tailored for the analysis of radium-226 and radium-228 in drinking water supplies from ground water and surface water sources and composites derived from them. The instructions have been adapted from several sources, including a draft EPA method. One objective was to minimize the generation of mixed wastes. Quantitative determinations of actinium-228 are made at 911 keV. The minimum detection level (MDL) for the gamma spectrometric measurements at this energy vary with matrix, volume, geometry, detector, background, and counting statistics. The range of MDL's for current detectors is 0.07 to 0.5 Bq/sample. Quantitative determinations of radium-226 are made by counting the high energy alpha particles which radium-226 progeny emit using liquid scintillation counting (LSC). The minimum detectable activity (MDA) is 3.8 E-3 Bq/sample. The maximum concentration which may be counted on available instruments without dilution is about 2 E + 5 Bq/sample. Typically, this determination of radium in a 2 L sample has a yield of 80%. If radium-228 is determined using a 16 h count after 50 h grow-in, the typical MDL is 1 E-9 to 8 E-9 μCi/mL (1 to 8 pCi/L). If radium-226 is determined using a 2.5 h count after 150 h grow-in, the typical MDA is about 1 E-10 μCi/mL (0. 1 pCi/L)

Determination of radium in water

Energy Technology Data Exchange (ETDEWEB)

Hohorst, F.A.; Huntley, M.W.; Hartenstein, S.D.

1995-10-01

These detailed work instructions (DWIs) are tailored for the analysis of radium-226 and radium-228 in drinking water supplies from ground water and surface water sources and composites derived from them. The instructions have been adapted from several sources, including a draft EPA method. One objective was to minimize the generation of mixed wastes. Quantitative determinations of actinium-228 are made at 911 keV. The minimum detection level (MDL) for the gamma spectrometric measurements at this energy vary with matrix, volume, geometry, detector, background, and counting statistics. The range of MDL`s for current detectors is 0.07 to 0.5 Bq/sample. Quantitative determinations of radium-226 are made by counting the high energy alpha particles which radium-226 progeny emit using liquid scintillation counting (LSC). The minimum detectable activity (MDA) is 3.8 E-3 Bq/sample. The maximum concentration which may be counted on available instruments without dilution is about 2 E + 5 Bq/sample. Typically, this determination of radium in a 2 L sample has a yield of 80%. If radium-228 is determined using a 16 h count after 50 h grow-in, the typical MDL is 1 E-9 to 8 E-9 {mu}Ci/mL (1 to 8 pCi/L). If radium-226 is determined using a 2.5 h count after 150 h grow-in, the typical MDA is about 1 E-10 {mu}Ci/mL (0. 1 pCi/L).

Chronic Beryllium Disease

Science.gov (United States)

... who are exposed to beryllium will not experience health effects. Studies have shown that on average, 1 – 6 percent of exposed workers develop beryllium sensitization, although the rates can be ...

Defense programs beryllium good practice guide

Energy Technology Data Exchange (ETDEWEB)

Herr, M.

1997-07-01

Within the DOE, it has recently become apparent that some contractor employees who have worked (or are currently working) with and around beryllium have developed chronic beryllium disease (CBD), an occupational granulomatous lung disorder. Respiratory exposure to aerosolized beryllium, in susceptible individuals, causes an immunological reaction that can result in granulomatous scarring of the lung parenchyma, shortness of breath, cough, fatigue, weight loss, and, ultimately, respiratory failure. Beryllium disease was originally identified in the 1940s, largely in the fluorescent light industry. In 1950, the Atomic Energy Commission (AEC) introduced strict exposure standards that generally curtailed both the acute and chronic forms of the disease. Beginning in 1984, with the identification of a CBD case in a DOE contractor worker, there was increased scrutiny of both industrial hygiene practices and individuals in this workforce. To date, over 100 additional cases of beryllium-specific sensitization and/or CBD have been identified. Thus, a disease previously thought to be largely eliminated by the adoption of permissible exposure standards 45 years ago is still a health risk in certain workforces. This good practice guide forms the basis of an acceptable program for controlling workplace exposure to beryllium. It provides (1) Guidance for minimizing worker exposure to beryllium in Defense Programs facilities during all phases of beryllium-related work, including the decontamination and decommissioning (D&D) of facilities. (2) Recommended controls to be applied to the handling of metallic beryllium and beryllium alloys, beryllium oxide, and other beryllium compounds. (3) Recommendations for medical monitoring and surveillance of workers exposed (or potentially exposed) to beryllium, based on the best current understanding of beryllium disease and medical diagnostic tests available. (4) Site-specific safety procedures for all processes of beryllium that is likely to

Defense programs beryllium good practice guide

International Nuclear Information System (INIS)

Herr, M.

1997-07-01

Within the DOE, it has recently become apparent that some contractor employees who have worked (or are currently working) with and around beryllium have developed chronic beryllium disease (CBD), an occupational granulomatous lung disorder. Respiratory exposure to aerosolized beryllium, in susceptible individuals, causes an immunological reaction that can result in granulomatous scarring of the lung parenchyma, shortness of breath, cough, fatigue, weight loss, and, ultimately, respiratory failure. Beryllium disease was originally identified in the 1940s, largely in the fluorescent light industry. In 1950, the Atomic Energy Commission (AEC) introduced strict exposure standards that generally curtailed both the acute and chronic forms of the disease. Beginning in 1984, with the identification of a CBD case in a DOE contractor worker, there was increased scrutiny of both industrial hygiene practices and individuals in this workforce. To date, over 100 additional cases of beryllium-specific sensitization and/or CBD have been identified. Thus, a disease previously thought to be largely eliminated by the adoption of permissible exposure standards 45 years ago is still a health risk in certain workforces. This good practice guide forms the basis of an acceptable program for controlling workplace exposure to beryllium. It provides (1) Guidance for minimizing worker exposure to beryllium in Defense Programs facilities during all phases of beryllium-related work, including the decontamination and decommissioning (D ampersand D) of facilities. (2) Recommended controls to be applied to the handling of metallic beryllium and beryllium alloys, beryllium oxide, and other beryllium compounds. (3) Recommendations for medical monitoring and surveillance of workers exposed (or potentially exposed) to beryllium, based on the best current understanding of beryllium disease and medical diagnostic tests available. (4) Site-specific safety procedures for all processes of beryllium that is

Removal of Radium-226 from Radium-Contaminated Soil using Distilled Water and Humic Acid: Effect of pH

International Nuclear Information System (INIS)

Phillips, E.; Muhammad Samudi Yasir; Muhamat Omar

2011-01-01

Effect of washing solutions' pH removal of radium-226 from radium-contaminated soil using distilled water and humic acid extracted from Malaysian peat soil was studied by batch washing method. The study encompassed the extraction of humic acid and the washing of radium-contaminated soil using distilled water and humic acid solutions of 100 ppm, both with varying pHs in the range of 3 to 11. The radioactivity concentration of radium-226 was determined by gamma spectrometer.The removal of radium-226 was greater when humic acid solutions were used compared to distilled water at the pH range studied and both washing solutions showed greater removal of radium-226 when basic solutions were used. Nevertheless, comparable removal efficiencies were observed when neutral and highly basic humic acid solutions were used. (author)

Radium contamination in the Nizzana-1 water well, Negev Desert, Israel

International Nuclear Information System (INIS)

Minster, T.; Ilani, S.; Kronfeld, J.; Even, O.; Godfrey-Smith, D.I.

2004-01-01

In a search for fresh groundwater reserves in the northwestern Negev Desert of Israel, the Nizzana-1 water well drilled into the Judea Group aquifer encountered water that exhibits an anomalously high 226 Ra activity of 2.4 Bq/l, along with 133 Bq/l 222 Rn. The exploited well water is a mixture of the original Judea Group aquifer water and the underlying more saline artesian water of the Kurnub Group (or Nubian Sandstone) aquifer that is currently intruding via faults. Both aquifers elsewhere contain intrinsically low radioactivity. A study of the sedimentary sequence transected by the borehole revealed that much of the bituminous sequence of the Mount Scopus Group of Upper Cretaceous age is substantially depleted in 226 Ra. During its ascent, the Nubian Sandstone water flushes the moderately uranium enriched bituminous sediments, selectively leaching radium and/or receiving alpha-recoil additions of radium. These bituminous chalks and marls are regionally widespread. It is thus suggested that radium should be monitored where faulting allows for inter-aquiferial connections across uranium enriched bituminous sections

Radium contamination in the Nizzana-1 water well, Negev Desert, Israel

Energy Technology Data Exchange (ETDEWEB)

Minster, T. E-mail: tsevi.minster@mail.gsi.gov.il; Ilani, S.; Kronfeld, J.; Even, O.; Godfrey-Smith, D.I

2004-07-01

In a search for fresh groundwater reserves in the northwestern Negev Desert of Israel, the Nizzana-1 water well drilled into the Judea Group aquifer encountered water that exhibits an anomalously high {sup 226}Ra activity of 2.4 Bq/l, along with 133 Bq/l {sup 222}Rn. The exploited well water is a mixture of the original Judea Group aquifer water and the underlying more saline artesian water of the Kurnub Group (or Nubian Sandstone) aquifer that is currently intruding via faults. Both aquifers elsewhere contain intrinsically low radioactivity. A study of the sedimentary sequence transected by the borehole revealed that much of the bituminous sequence of the Mount Scopus Group of Upper Cretaceous age is substantially depleted in {sup 226}Ra. During its ascent, the Nubian Sandstone water flushes the moderately uranium enriched bituminous sediments, selectively leaching radium and/or receiving alpha-recoil additions of radium. These bituminous chalks and marls are regionally widespread. It is thus suggested that radium should be monitored where faulting allows for inter-aquiferial connections across uranium enriched bituminous sections.

Thermomechanical testing of beryllium for the JET/ISX-B beryllium limiter experiment

International Nuclear Information System (INIS)

Watson, R.D.; Smith, M.F.; Whitley, J.B.; McDonald, J.M.

1984-01-01

Materials testing of S-65-B beryllium has been conducted in support of the beryllium limiter experiment on the ISX-B tokamak. The S-65-B grade of hot-pressed beryllium was chosen over S-200-E because of its superior strength and ductility at elevated temperatures. The testing has included measurement of tensile and yield strength, ductility, Young's Modulus, thermal conductivity, and specific heat from 50 0 C to 700 0 C. Thermal fatigue testing of a 2.5 cm beryllium cube was conducted using an electron beam to apply a heat flux of 2.5 kw/cm 2 for 0.3 second pulses for 1500 cycles. Results from the tests are compared to elastic-plastic finite element stress calculations. The testing indicates that the ISX-B beryllium limiter should survive the tokamak environment without serious structural failure, although some surface cracking is expected to occur. (author)

Spectroscopy of neutral radium

Energy Technology Data Exchange (ETDEWEB)

Mol, Aran; De, Subhadeep; Jungmann, Klaus; Wilschut, Hans; Willmann, Lorenz [KVI, University of Groningen, Groningen (Netherlands)

2008-07-01

The heavy alkaline earth atoms radium is uniquely sensitive towards parity and time reversal symmetry violations due to a large enhancement of an intrinsic permanent electric dipole moment of the nucleous or the electron. Furthermore, radium is sensitive to atomic parity violation and the nuclear anapole moment. To prepare such experiments spectroscopy of relevant atomic states need to be done. At a later stage we will build a neutral atom trap for radium. We have built an atomic beam of the short lived isotope {sup 225}Ra with a flux of several 10{sup 4} atoms/sec. We are preparing the laser spectroscopy using this beam setup. In the preparation for efficient laser cooling and trapping we have successfully trapped barium, which is similar in it's requirements for laser cooling. The techniques which we have developed with barium can be used to trap rare radium isotopes. We report on the progress of the experiments.

Beryllium allergy

International Nuclear Information System (INIS)

Schoenherr, S.; Pevny, I.

1989-12-01

Beryllium is not only a high potent allergen, but also a fotoallergen and can provoke contact allergic reactions, fotoallergic reactions, granulomatous skin reactions, pulmonary granulomatous diseases and sometimes even systemic diseases. The authors present 9 own cases of a patch test positive beryllium allergy, 7 patients with relevant allergy and 5 patients with an allergic contact stomatitis. (author)

Problems in the separation of radium from uranium ore tailings

Energy Technology Data Exchange (ETDEWEB)

Seeley, F.G.

1976-01-01

The radium content of a representative sandstone type of uranium ore was found to be distributed uniformly according to particle size before leaching, but in sulfuric acid-leached tailings was found predominantly in the -325 mesh fraction. The radium leaching characteristics from both ore and sulfate-leached tailings were investigated. Several 1 M salt solutions showed poor to moderate RaSO/sub 4/ dissolution from ''slimes solids'' tailings, while 3 M HNO/sub 3/ or HCl solutions dissolved approximately 95% of the radium content of either ore or tailings. Tests are reported in which -325 mesh sand particles were coated with alkaline-earth sulfates by a special technique to simulate slime solids tailings. The dissolution of RaSO/sub 4/ from these coated sands was decreased by the presence of BaSO/sub 4/, but increased by the presence of CaSO/sub 4/. The interrelationships in the dissolution of mixtures of CaSO/sub 5/, SrSO/sub 4/, BaSO/sub 4/, and RaSO/sub 4/ are shown, and a generalized equation for the estimation of the dissolution of a minor component is presented.

Radium diagnosis campaign - 59327

International Nuclear Information System (INIS)

Gabillaud Poillion, Florence

2012-01-01

In line with the approaches already adopted in France during the 90's on various sites where research and/or radium-extraction activities were mostly conducted in the past, the French public authorities wish from now on to pursue their prevention and site-rehabilitation approach inherited from the French craftsman and medical sectors that used that radioelement. As a matter of fact, radium has been in use in several medical activities, notably in the initial methods of cancer therapy. Similarly, it was also used in some craftsman activities, such as the clock industry, for its radioluminescent properties, the fabrication of lightning conductors or cosmetics until the 60's. Those activities have generated various traces of pollution that have remained today. On the basis of the different inventories of industrial sites where radium may have been held or used, and notably the inventory updated by the French Institute for Radiation Protection and Nuclear Safety (Institut de radioprotection et de surete nucleaire - IRSN) in 2007 at the request of the French Nuclear Safety Authority (Autorite de surete nucleaire - ASN), French State services have potentially identified 134 sites that hosted radium-related activities in France. The radiological status of those sites is either unknown or very partially known by State services. Sites include both dwellings or commercial premises and derelict lands. The 'Radium Diagnosis Campaign' (Operation Diagnostic Radium), consists of a radiological survey carried out by the IRSN. In cases where traces of radium are detected, plans call for the implementation of precautionary measures and of a medical follow-up of the relevant populations. Lastly, radium-contaminated sites are rehabilitated by the French National Radioactive Waste Management Agency (Agence nationale pour la gestion des dechets radioactifs - Andra). That voluntary and positive approach on the part of public authorities is fully financed by public funds, and consequently

Measurements of beryllium sputtering yields at JET

Science.gov (United States)

Jet-Efda Contributors Stamp, M. F.; Krieger, K.; Brezinsek, S.

2011-08-01

The lifetime of the beryllium first wall in ITER will depend on erosion and redeposition processes. The physical sputtering yields for beryllium (both deuterium on beryllium (Be) and Be on Be) are of crucial importance since they drive the erosion process. Literature values of experimental sputtering yields show an order of magnitude variation so predictive modelling of ITER wall lifetimes has large uncertainty. We have reviewed the old beryllium yield experiments on JET and used current beryllium atomic data to produce revised beryllium sputtering yields. These experimental measurements have been compared with a simple physical sputtering model based on TRIM.SP beryllium yield data. Fair agreement is seen for beryllium yields from a clean beryllium limiter. However the yield on a beryllium divertor tile (with C/Be co-deposits) shows poor agreement at low electron temperatures indicating that the effect of the higher sputtering threshold for beryllium carbide is important.

Do pyrotechnics contain radium?

International Nuclear Information System (INIS)

Steinhauser, Georg; Musilek, Andreas

2009-01-01

Many pyrotechnic devices contain barium nitrate which is used as an oxidizer and colouring agent primarily for green-coloured fireworks. Similarly, strontium nitrate is used for red-coloured pyrotechnic effects. Due to their chemical similarities to radium, barium and strontium ores can accumulate radium, causing a remarkable activity in these minerals. Radium in such contaminated raw materials can be processed together with the barium or strontium, unless extensive purification of the ores was undertaken. For example, the utilization of 'radiobarite' for the production of pyrotechnic ingredients can therefore cause atmospheric pollution with radium aerosols when the firework is displayed, resulting in negative health effects upon inhalation of these aerosols. In this study, we investigated the occurrence of gamma-photon-emitting radionuclides in several pyrotechnic devices. The highest specific activities were due to K-40 (up to 20 Bq g -1 , average value 14 Bq g -1 ). Radium-226 activities were in the range of 16-260 mBq g -1 (average value 81 mBq g -1 ). Since no uranium was found in any of the samples, indeed, a slight enrichment of Ra-226 in coloured pyrotechnics can be observed. Radioactive impurities stemming from the Th-232 decay chain were found in many samples as well. In the course of novel developments aiming at the 'greening' of pyrotechnics, the potential radioactive hazard should be considered as well.

Radium in consumer products: an historical perspective

International Nuclear Information System (INIS)

Holm, W.M.

1978-01-01

This paper demonstrates in historical and technical perspective how radium began to be used in consumer products and how changing conditions in technology and regulations have greatly modified the use of radium. In addition, the various uses of radium that have been tried or have been used in consumer products have been described, and whenever possible, the historical perspective has been used to show when devices were needed and when changing conditions caused the products to be no longer required. The historical perspective attitude is again used in the evaluation of the risks and benefits of radium in comparison to radium substitutes

Beryllium R&D for blanket application

Science.gov (United States)

Donne, M. Dalle; Longhurst, G. R.; Kawamura, H.; Scaffidi-Argentina, F.

1998-10-01

The paper describes the main problems and the R&D for the beryllium to be used as neutron multiplier in blankets. As the four ITER partners propose to use beryllium in the form of pebbles for their DEMO relevant blankets (only the Russians consider the porous beryllium option as an alternative) and the ITER breeding blanket will use beryllium pebbles as well, the paper is mainly based on beryllium pebbles. Also the work on the chemical reactivity of fully dense and porous beryllium in contact with water steam is described, due to the safety importance of this point.

Corrosion of beryllium oxide; Corrosion de l'oxyde de beryllium

Energy Technology Data Exchange (ETDEWEB)

Elston, J; Caillat, R [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1958-07-01

Data are reported on the volatilization rate of beryllium oxide in moist air depending on temperature and water vapour concentration. They are concerned with powder samples or sintered shapes of various densities. For sintered samples, the volatilization rate is very low under the following conditions: - temperature: 1300 deg. C, - water vapour concentration in moist air: 25 g/m{sup 3}, - flow rate: 12 I/hour corresponding to a speed of 40 m/hour on the surface of the sample. For calcinated powders (1300 deg. C), grain growth has been observed under a stream of moist air at 1100 deg. C. For instance, grain size changes from 0,5 to at least 2 microns after 500 hours of exposure at this temperature. Furthermore, results data are reported on corrosion of sintered beryllium oxide in pressurized water. At 250 deg. C, under a pressure of 40 kg/cm{sup 2} water is very slightly corrosive; however, internal strains are revealed. Finally, some features on the corrosion in liquid sodium are exposed. (author)Fren. [French] La volatilisation de l'oxyde de beryllium dans l'air humide est etudiee en fonction de la temperature pour differentes teneurs de vapeur d'eau. Les essais decrits portent sur de l'oxyde de beryllium en poudre ou sur des echantillons d'oxyde de beryllium fritte de differentes densites. Avec un debit d'air de 12 I/h contenant 25 g de vapeur par m{sup 3} correspondant a une vitesse de 40 m/h sur la surface de l'echantillon, la volatilisation des frittes a 1300 deg. C reste tres faible. Sur de la poudre d'oxyde de beryllium calcinee initialement a 1300 deg. C, on observe un grossissement de la taille des grains sous l'influence de l'air humide a 1100 deg. C. Par exemple, elle passe de 0,5 a au moins 2 microns apres 500 heures d'exposition a cette temperature. On donne d'autre part les resultats d'une etude de la corrosion de frittes d'oxyde de beryllium par l'eau, en autoclave. A 250 deg. C, sous une pression de 40 kg/cm{sup 2}, l'action de l'eau reste tres

Port Radium Canada's Original Radium/Uranium Mine, The Complete Story of Canada's Historic Radium/Uranium Mine, 1932 to 2012 - 13159

International Nuclear Information System (INIS)

Chambers, Doug; Wiatzka, Gerd; Brown, Steve

2013-01-01

This paper provides the life story of Canada's original radium/uranium mine. In addition to the history of operations, it discusses the unique and successful approach used to identify the key issues and concerns associated with the former radium, uranium and silver mining property and the activities undertaken to define the remedial actions and subsequent remedial plan. The Port Radium Mine site, situated approximately 275 km north of Yellowknife on the east shore of Great Bear Lake, Northwest Territories, was discovered in 1930 and underground mining began in 1932. The mine operated almost continuously from 1932 to 1982, initially for recovery of radium, then uranium and finally, for recovery of silver. Tailings production totaled an estimated 900,000 tons and 800,000 tons from uranium and silver processing operations respectively. In the early days of mining, Port Radium miners were exposed to radon and associated decay product levels (in Working Level Months of exposure - WLM) hundreds of times greater than modern standards. The experience of the Port Radium miners provides important contribution to understanding the risks from radon. While the uranium mine was originally decommissioned in the early 1960's, to the standards of the day, the community of Deline (formerly Fort Franklin) had concerns about residual contamination at the mine site and the potential effects arising from use of traditional lands. The Deline people were also concerned about the possible risks to Deline Dene arising from their work as ore carriers. In the late 1990's, the community of Deline brought these concerns to national attention and consequently, the Government of Canada and the community of Deline agreed to move forward in a collaborative manner to address these concerns. The approach agreed to was to establish the Canada-Deline Uranium Table (CDUT) to provide a joint process by which the people of Deline could have their concerns expressed and addressed. A great deal of work was

Ageing Management of Beryllium and Graphite Blocks in Research Reactor MARIA

Energy Technology Data Exchange (ETDEWEB)

Golab, A. [National Centre for Nuclear Research, Warsaw (Poland)

2013-07-01

In the paper the phenomenon of beryllium moderator poisoning by thermal neutron absorption and the method and results of this phenomenon control is presented. Also the phenomenon of graphite blocks damage due to fast neutrons accumulation and the methods and results of this process supervising is described. These methods refer especially to: visual inspection of their state and radiography of graphite blocks. Special attention is paid to permanent estimate of fast neutron fluency accumulated in blocks and methods of their shuffling in the reactor core. The shuffling makes possible to increase the lifetime of beryllium and graphite blocks and decrease the cost of reactor operation.

Comparison of radiological changes in humans exposed to radium and in beagle dogs injected with radium

International Nuclear Information System (INIS)

Morgan, J.P.; Kirsh, J.E.; Pool, R.R.

1982-01-01

Data from MIT and New Jersey studies were combined with data from the Center for Human Radiobiology, Argonne National Laboratory, to create a material of 2259 persons occupationaly exposed to radium. The population studied consisted of radium-dial painters, radium chemists, and persons who had received radium in past years in attempts to treat various medical conditions. Within a colony of beagle dogs at the LEHR, UCD, which received eight semi-monthly injections of 226 Ra were 28 dogs that received a dosage of 80 to 130 times maximum permissible skeletal burden for man (0.1 μCi 226 Ra). The intravenous injections of 226 Ra began at 435 days of age

Thermal effects on beryllium mirrors

International Nuclear Information System (INIS)

Weinswig, S.

1989-01-01

Beryllium is probably the most frequently used material for spaceborne system scan mirrors. Beryllium's properties include lightweightedness, high Young's modulus, high stiffness value, high resonance value. As an optical surface, beryllium is usually nickel plated in order to produce a higher quality surface. This process leads to the beryllium mirror acting like a bimetallic device. The mirror's deformation due to the bimetallic property can possibly degrade the performance of the associated optical system. As large space borne systems are designed and as temperature considerations become more crucial in the instruments, the concern about temporal deformation of the scan mirrors becomes a prime consideration. Therefore, two sets of tests have been conducted in order to ascertain the thermal effects on nickel plated beryllium mirrors. These tests are categorized. The purpose of this paper is to present the values of the bimetallic effect on typical nickel plated beryllium mirrors

Do pyrotechnics contain radium?

Energy Technology Data Exchange (ETDEWEB)

Steinhauser, Georg; Musilek, Andreas, E-mail: georg.steinhauser@ati.ac.a [Vienna University of Technology, Atominstitut der Oesterreichischen Universitaeten, Stadionallee 2, A-1020 Wien (Austria)

2009-07-15

Many pyrotechnic devices contain barium nitrate which is used as an oxidizer and colouring agent primarily for green-coloured fireworks. Similarly, strontium nitrate is used for red-coloured pyrotechnic effects. Due to their chemical similarities to radium, barium and strontium ores can accumulate radium, causing a remarkable activity in these minerals. Radium in such contaminated raw materials can be processed together with the barium or strontium, unless extensive purification of the ores was undertaken. For example, the utilization of 'radiobarite' for the production of pyrotechnic ingredients can therefore cause atmospheric pollution with radium aerosols when the firework is displayed, resulting in negative health effects upon inhalation of these aerosols. In this study, we investigated the occurrence of gamma-photon-emitting radionuclides in several pyrotechnic devices. The highest specific activities were due to K-40 (up to 20 Bq g{sup -1}, average value 14 Bq g{sup -1}). Radium-226 activities were in the range of 16-260 mBq g{sup -1} (average value 81 mBq g{sup -1}). Since no uranium was found in any of the samples, indeed, a slight enrichment of Ra-226 in coloured pyrotechnics can be observed. Radioactive impurities stemming from the Th-232 decay chain were found in many samples as well. In the course of novel developments aiming at the 'greening' of pyrotechnics, the potential radioactive hazard should be considered as well.

Overview of radium legacies in Belgium - 59367

International Nuclear Information System (INIS)

Dehandschutter, B.; Jadoul, L.; Mannaerts, K.; Pepin, S.; Poffijn, A.; Blommaert, W.; Sonck, M.

2012-01-01

The Belgian metallurgical company, Union Miniere, has been a key-player in the sector of radium production between 1922 and 1969. The factory based in Olen has extracted radium from minerals and produced radium sources during that period. The radium production facilities have been dismantled in the 70's but legacies of the former production have still to be remediated. An overview of these legacies and of their radiological characteristics will be given. Next to the sites related to radium production, other radium legacies are related to NORM industries, essentially from the phosphate sector (phosphogypsum and CaF 2 stacks). The issue of radium legacies in Belgium encompasses a variety of concrete situations. Next to the issue of the legacies of the former radium production, the other radium contaminated sites are related to current or former NORM industries, especially from the phosphate sector. The methodological and regulatory approaches towards these sites have been described elsewhere in these proceedings. The outcome differs according to the specificities of the site: it will not be the same for the legacies of former radium production where the inventory of radioactivity includes materials which have to be considered and treated as radioactive waste (for example, disused radium sources) than for phosphogypsum stacks where a sufficient level of protection may be brought by relatively simple measures such as restrictions on the use of the site. For these sites, like PG stacks, where radon is the most important exposure pathway in case of intrusion scenario, regulatory measures similar to the ones applied to 'radon-prone areas' (restrictions in the construction of buildings, compulsory radon monitoring in workplaces present on the site,...) may be implemented. In all cases, the radiological risk-assessment will be crucial for the decision-making process. The examples given showed that the probability of occurrence of 'intrusion scenario' (like construction of

The Environmental Behaviour of Radium: Revised Ed

Energy Technology Data Exchange (ETDEWEB)

NONE

2014-03-15

A number of industrial activities produce residues containing either uranium or thorium series radionuclides or both. These include the mining and milling of uranium and of other metalliferous and non-metallic ores; the production of coal, oil and gas; the extraction and purification of water; and the production of industrial minerals such as phosphates. Residues from such activities have become of increasing interest from a radiological impact assessment point of view in recent years and isotopes of radium are often of particular interest in such assessments. The IAEA attaches high importance to the dissemination of information that can assist Member States with the implementation and improvement of activities related to radiation safety standards, including management of radioactive residues containing natural radionuclides, such as radium isotopes. In 1990, the IAEA published Technical Reports Series No. 310 (TRS 310), The Environmental Behaviour of Radium. Since the publication of TRS 310, a considerable number of publications related to the environmental behaviour of radium have appeared in the literature. It was therefore considered timely to produce a replacement report providing up to date information on key transfer processes, concepts and models that are important in radiological assessments and environmental applications of radium. This report outlines radium behaviour in terrestrial, freshwater and marine environments. The primary objective of the report is to provide IAEA Member States with information for use in the radiological assessment of accidental releases and routine discharges of radium in the environment, and in remediation planning for areas contaminated by radium. Additionally, applications of radium isotopes as tracers of environmental processes are discussed.

Radium behaviour during ferric oxi-hydroxides crystallization

International Nuclear Information System (INIS)

Bassot, S.; Stammose, D.; Benitah, S.

2004-01-01

In uranium mill tailings, oxides and oxi-hydroxides are responsible of about 70% of the radium immobilization, half being associated to amorphous forms (mainly hydrous ferric oxides and hydrous manganese oxides). With time, crystallization of these amorphous forms can occur, inducing a redistribution of radium between solid and solution. If the amount of mobile radium increases, the impact of these tailings on the environment may become significant. The aim of this study is to determine the amount of radium released in solution during the crystallization process of hydrous ferric oxide (HFO). The transformation of Ra-HFO co-precipitate in crystallized forms (goethite, hematite, is studied by ageing at 40 deg C for different solution compositions. Both solids and solutions are sampled for different times and analysed. The solid evolution is followed by specific area measurements (about 250 m2/g for HFO and about 10-20 m 2 /g for crystallized form) and by determination of the amorphous fraction according to a selective extraction procedure. The solutions were analysed for 226 radium activity, iron concentration and pH. In order to discriminate the part of radium included in the solid and the part of radium fixed on the solid surface, radium sorption onto HFO and crystallized forms is studied as a function of pH. The modelling of the sorption curves with JCHESS 2.0 code allow to point out the mechanisms responsible of the 226-radium distribution between solid and solution during the crystallization process of HFO. (author)

The Environmental Behaviour of Radium: Revised Ed

International Nuclear Information System (INIS)

2014-01-01

A number of industrial activities produce residues containing either uranium or thorium series radionuclides or both. These include the mining and milling of uranium and of other metalliferous and non-metallic ores; the production of coal, oil and gas; the extraction and purification of water; and the production of industrial minerals such as phosphates. Residues from such activities have become of increasing interest from a radiological impact assessment point of view in recent years and isotopes of radium are often of particular interest in such assessments. The IAEA attaches high importance to the dissemination of information that can assist Member States with the implementation and improvement of activities related to radiation safety standards, including management of radioactive residues containing natural radionuclides, such as radium isotopes. In 1990, the IAEA published Technical Reports Series No. 310 (TRS 310), The Environmental Behaviour of Radium. Since the publication of TRS 310, a considerable number of publications related to the environmental behaviour of radium have appeared in the literature. It was therefore considered timely to produce a replacement report providing up to date information on key transfer processes, concepts and models that are important in radiological assessments and environmental applications of radium. This report outlines radium behaviour in terrestrial, freshwater and marine environments. The primary objective of the report is to provide IAEA Member States with information for use in the radiological assessment of accidental releases and routine discharges of radium in the environment, and in remediation planning for areas contaminated by radium. Additionally, applications of radium isotopes as tracers of environmental processes are discussed

Sintering of beryllium oxide; Frittage de l'oxyde de beryllium

Energy Technology Data Exchange (ETDEWEB)

Caillat, R; Pointud, R [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1955-07-01

This study had for origin to find a process permitting to manufacture bricks of beryllium oxide of pure nuclear grade, with a density as elevated as possible and with standardized shape. The sintering under load was the technique kept for the manufacture of the bricks. Because of the important toxicity of the beryllium oxide, the general features for the preliminary study of the sintering, have been determined while using alumina. The obtained results will be able to act as general indication for ulterior studies with sintering under load. (M.B.) [French] Cette etude a eu pour origine la recherche d'un procede permettant de fabriquer industriellement des briques d'oxyde de beryllium nucleaireraent pures, de densite aussi elevee que possible et de forme standardisee. Le frittage sous charge fut la technique retenue pour la fabrication des briques. En raison de la grande toxicite de l'oxyde de beryllium, les caracteristiques generales du frittage, pour l'etude preliminaire, ont ete determine en utilisant de l'alumine. Les resultats obtenus pourront servir d'indication generale pour des etudes ulterieurs avec frittage sous charge. (M.B.)

Fracture toughness of irradiated beryllium

International Nuclear Information System (INIS)

Beeston, J.M.

1978-01-01

The fracture toughness of nuclear grade hot-pressed beryllium upon irradiation to fluences of 3.5 to 5.0 x 10 21 n/cm 2 , E greater than 1 MeV, was determined. Procedures and data relating to a round-robin test contributing to a standard ASTM method for unirradiated beryllium are discussed in connection with the testing of irradiated specimens. A porous grade of beryllium was also irradiated and tested, thereby enabling some discrimination between the models for describing the fracture toughness behavior of porous beryllium. The fracture toughness of unirradiated 2 percent BeO nuclear grade beryllium was 12.0 MPa m/sup 1 / 2 /, which was reduced 60 percent upon irradiation at 339 K and testing at 295 K. The fracture toughness of a porous grade of beryllium was 13.1 MPa m/sup 1 / 2 /, which was reduced 68 percent upon irradiation and testing at the same conditions. Reasons for the reduction in fracture toughness upon irradiation are discussed

Radium: a miracle cure{exclamation_point} (invited paper)

Energy Technology Data Exchange (ETDEWEB)

Genet, M

1998-07-01

In 1896, the general population had little enthusiasm for the recent discovery of radioactivity by Henri Becquerel. There was certainly much less than for X rays which had appeared, 3 months earlier, as a 'magic radiation'. However, polonium and radium, discovered by the Curies in 1898, aroused new interest in 'uranic rays'. The first weighable amounts of radium, prepared at the beginning of this century, were used for medical applications. Immediately, the therapeutic properties of radium rays against cancer were recognised. The use of radium in medicine became so common that every kind of disease was treated by radium therapy: not only breast cancer, but also, diabetes, sciatica, uraemia, rheumatism, and even impotence{exclamation_point} As a consequence of this tremendous success, the radium industry grew rapidly during the 1920s and numerous goods, especially cosmetics, doped with radium were on sale. It was even considered that in order to be in good health, one should drink a glass of radioactive water every day, prepared by using a radium percolator. This period lasted for more than 25 years, then, just before World War II radium use was considered dangerous and the number of its applications decreased. (author)

Beryllium-stimulated neopterin as a diagnostic adjunct in chronic beryllium disease.

Science.gov (United States)

Maier, Lisa A; Kittle, Lori A; Mroz, Margaret M; Newman, Lee S

2003-06-01

The diagnosis of chronic beryllium disease (CBD) relies on the beryllium lymphocyte proliferation test (BeLPT) to demonstrate a Be specific immune response. This test has improved early diagnosis, but cannot discriminate beryllium sensitization (BeS) from CBD. We previously found high neopterin levels in CBD patients' serum and questioned whether Be-stimulated neopterin production by peripheral blood cells in vitro might be useful in the diagnosis of CBD. CBD, BeS, Be exposed workers without disease (Be-exp) normal controls and sarcoidosis subjects were enrolled. Peripheral blood mononuclear cells (PBMN) were cultured in the presence and absence of beryllium sulfate. Neopterin levels were determined from cell supernatants by enzyme linked immunosorbent assay (ELISA). Clinical evaluation of CBD subjects included chest radiography, pulmonary function testing, exercise testing, and the BeLPT. CBD patients produced higher levels of neopterin in both unstimulated and Be-stimulated conditions compared to all other subjects (P workplace screening. Copyright 2003 Wiley-Liss, Inc.

OVERVIEW OF BERYLLIUM SAMPLING AND ANALYSIS

Energy Technology Data Exchange (ETDEWEB)

Brisson, M

2009-04-01

Because of its unique properties as a lightweight metal with high tensile strength, beryllium is widely used in applications including cell phones, golf clubs, aerospace, and nuclear weapons. Beryllium is also encountered in industries such as aluminium manufacturing, and in environmental remediation projects. Workplace exposure to beryllium particulates is a growing concern, as exposure to minute quantities of anthropogenic forms of beryllium may lead to sensitization and to chronic beryllium disease, which can be fatal and for which no cure is currently known. Furthermore, there is no known exposure-response relationship with which to establish a 'safe' maximum level of beryllium exposure. As a result, the current trend is toward ever lower occupational exposure limits, which in turn make exposure assessment, both in terms of sampling and analysis, more challenging. The problems are exacerbated by difficulties in sample preparation for refractory forms of beryllium, such as beryllium oxide, and by indications that some beryllium forms may be more toxic than others. This chapter provides an overview of sources and uses of beryllium, health risks, and occupational exposure limits. It also provides a general overview of sampling, analysis, and data evaluation issues that will be explored in greater depth in the remaining chapters. The goal of this book is to provide a comprehensive resource to aid personnel in a wide variety of disciplines in selecting sampling and analysis methods that will facilitate informed decision-making in workplace and environmental settings.

Toxicokinetics of beryllium following inhalation of beryllium oxide by Beagle dogs. III

International Nuclear Information System (INIS)

Finch, G.L.; Haley, P.J.; Hoover, M.D.; Mewhinney, J.A.; Bice, D.E.; Eidson, A.F.

1988-01-01

Young adult Beagle dogs inhaled radiolabeled beryllium oxide aerosols ( 7 BeO) prepared at either 500 deg. or 1000 deg. C to achieve one of two initial lung burdens (ILBs) of BeO. After exposure, animals were monitored by whole body counting for 7 Be, and excreta, clinical, and radiographic data were collected. One group of dogs was assigned for serial sacrifice for quantitation of beryllium clearance from lung, translocation to other organs, and histopathologic analysis of lung and lymph nodes. A second group of dogs was subjected to periodic bronchopulmonary lavage for analysis of lymphocyte responsiveness to beryllium. These latter dogs were subsequently re-exposed to the high ILB level of BeO prepared t 500 deg. C. ILBs following the second exposure were higher than that after the first exposure (74 vs. 42 μg BeO/kg, respectively). Except for one dog that exhibited enhanced beryllium retention after the second exposure, patterns of whole body clearance were similar to those observed after the initial exposures to the 500 deg. C-BeO. Analysis of lymphocyte responsiveness to beryllium in the second group of dogs is continuing. (author)

Toxicokinetics of beryllium following inhalation of beryllium oxide by Beagle dogs. III

Energy Technology Data Exchange (ETDEWEB)

Finch, G L; Haley, P J; Hoover, M D; Mewhinney, J A; Bice, D E; Eidson, A F

1988-12-01

Young adult Beagle dogs inhaled radiolabeled beryllium oxide aerosols ({sup 7}BeO) prepared at either 500 deg. or 1000 deg. C to achieve one of two initial lung burdens (ILBs) of BeO. After exposure, animals were monitored by whole body counting for {sup 7}Be, and excreta, clinical, and radiographic data were collected. One group of dogs was assigned for serial sacrifice for quantitation of beryllium clearance from lung, translocation to other organs, and histopathologic analysis of lung and lymph nodes. A second group of dogs was subjected to periodic bronchopulmonary lavage for analysis of lymphocyte responsiveness to beryllium. These latter dogs were subsequently re-exposed to the high ILB level of BeO prepared t 500 deg. C. ILBs following the second exposure were higher than that after the first exposure (74 vs. 42 {mu}g BeO/kg, respectively). Except for one dog that exhibited enhanced beryllium retention after the second exposure, patterns of whole body clearance were similar to those observed after the initial exposures to the 500 deg. C-BeO. Analysis of lymphocyte responsiveness to beryllium in the second group of dogs is continuing. (author)

Optimization of beryllium for fusion blanket applications

International Nuclear Information System (INIS)

Billone, M.C.

1993-01-01

The primary function of beryllium in a fusion reactor blanket is neutron multiplication to enhance tritium breeding. However, because heat, tritium and helium will be generated in and/or transported through beryllium and because the beryllium is in contact with other blanket materials, the thermal, mechanical, tritium/helium and compatibility properties of beryllium are important in blanket design. In particular, tritium retention during normal operation and release during overheating events are safety concerns. Accommodating beryllium thermal expansion and helium-induced swelling are important issues in ensuring adequate lifetime of the structural components adjacent to the beryllium. Likewise, chemical/metallurgical interactions between beryllium and structural components need to be considered in lifetime analysis. Under accident conditions the chemical interaction between beryllium and coolant and breeding materials may also become important. The performance of beryllium in fusion blanket applications depends on fabrication variables and operational parameters. First the properties database is reviewed to determine the state of knowledge of beryllium performance as a function of these variables. Several design calculations are then performed to indicate ranges of fabrication and operation variables that lead to optimum beryllium performance. Finally, areas for database expansion and improvement are highlighted based on the properties survey and the design sensitivity studies

Reactivity test between beryllium and copper

International Nuclear Information System (INIS)

Kawamura, H.; Kato, M.

1995-01-01

Beryllium has been expected for using as plasma facing material on ITER. And, copper alloy has been proposed as heat sink material behind plasma facing components. Therefore, both materials must be joined. However, the elementary process of reaction between beryllium and copper alloy does not clear in detail. For example, other authors reported that beryllium reacted with copper at high temperature, but it was not obvious about the generation of reaction products and increasing of the reaction layer. In the present work, from this point, for clarifying the elementary process of reaction between beryllium and copper, the out-of-pile compatibility tests were conducted with diffusion couples of beryllium and copper which were inserted in the capsule filled with high purity helium gas (6N). Annealing temperatures were 300, 400, 500, 600 and 700 degrees C, and annealing periods were 100, 300 and 1000h. Beryllium specimens were hot pressed beryllium, and copper specimens were OFC (Oxygen Free Copper)

Method for fabricating beryllium structures

Science.gov (United States)

Hovis, Jr., Victor M.; Northcutt, Jr., Walter G.

1977-01-01

Thin-walled beryllium structures are prepared by plasma spraying a mixture of beryllium powder and about 2500 to 4000 ppm silicon powder onto a suitable substrate, removing the plasma-sprayed body from the substrate and placing it in a sizing die having a coefficient of thermal expansion similar to that of the beryllium, exposing the plasma-sprayed body to a moist atmosphere, outgassing the plasma-sprayed body, and then sintering the plasma-sprayed body in an inert atmosphere to form a dense, low-porosity beryllium structure of the desired thin-wall configuration. The addition of the silicon and the exposure of the plasma-sprayed body to the moist atmosphere greatly facilitate the preparation of the beryllium structure while minimizing the heretofore deleterious problems due to grain growth and grain orientation.

Beryllium technology workshop, Clearwater Beach, Florida, November 20, 1991

International Nuclear Information System (INIS)

Longhurst, G.R.

1991-12-01

This report discusses the following topics: beryllium in the ITER blanket; mechanical testing of irradiated beryllium; tritium release measurements on irradiated beryllium; beryllium needs for plasma-facing components; thermal conductivity of plasma sprayed beryllium; beryllium research at the INEL; Japanese beryllium research activities for in-pile mockup tests on ITER; a study of beryllium bonding of copper alloy; new production technologies; thermophysical properties of a new ingot metallurgy beryllium product line; implications of beryllium:steam interactions in fusion reactors; and a test program for irradiation embrittlement of beryllium at JET

Beryllium technology workshop, Clearwater Beach, Florida, November 20, 1991

Energy Technology Data Exchange (ETDEWEB)

Longhurst, G.R.

1991-12-01

This report discusses the following topics: beryllium in the ITER blanket; mechanical testing of irradiated beryllium; tritium release measurements on irradiated beryllium; beryllium needs for plasma-facing components; thermal conductivity of plasma sprayed beryllium; beryllium research at the INEL; Japanese beryllium research activities for in-pile mockup tests on ITER; a study of beryllium bonding of copper alloy; new production technologies; thermophysical properties of a new ingot metallurgy beryllium product line; implications of beryllium:steam interactions in fusion reactors; and a test program for irradiation embrittlement of beryllium at JET.

Radioactive artifacts: historical sources of modern radium contamination

International Nuclear Information System (INIS)

Blaufox, M.D.

1988-01-01

Radium has been distributed in a wide variety of devices during the early part of this century. Antique objects containing significant amounts of radium turn up at flea markets, antique shows, and antique dealers, in a variety of locations. These objects include radium in devices which were used by legitimate medical practitioners for legitimate medical purposes such as therapy, as well as a wide variety of quack cures. These devices may contain anywhere from a few nanocuries to as much as several hundred microcuries of radium. In addition to medical sources, a large variety of scientific instruments utilize radium in luminous dials. These instruments include compasses, azimuth indicators, and virtually any object which might require some form of calibration. In addition, the consumer market utilized a large amount of radium in the production of wrist watches, pocket watches, and clocks with luminous dials. Some of these watches contained as much as 4.5 microCi of radium, and between 1913 and 1920 about 70 gm was produced for the manufacture of luminous compounds. In addition to the large amount of radium produced for scientific and consumer utilization, there were a number of materials produced which were claimed to contain radium but in fact did not, further adding to the confusion in this area. The wide availability of radium is a result of the public's great fascination with radioactivity during the early part of this century and a belief in its curative properties. A number of objects were produced in order to trap the emanations of radium in water for persons to drink in order to benefit from their healing effects. Since the late 20s and early 30s the public's attitude towards radiation has shifted 180 degrees and it is now considered an extremely dangerous and harmful material

Preliminary study of radium-contaminated soils

Energy Technology Data Exchange (ETDEWEB)

Healy, J.W.; Rodgers, J.C.

1978-10-01

A preliminary study was made of the potential radiation exposures to people from radium-226 contamination in the soil in order to provide guidance on limits to be applied in decontaminating land. Pathways included were inhalation of radium from resuspension; ingestion of radium with foods; external gamma radiation from radium daughters; inhalation of radon and daughter, both in the open air and in houses; and the intake of /sup 210/Pb and /sup 210/Po from both inhalation and ingestion. The depth of the contaminated layer is of importance for external exposure and especially for radon emanation. The most limiting pathway was found to be emanation of the radon into buildings with limiting values comparable to those found naturally in many areas.

Preliminary study of radium-contaminated soils

International Nuclear Information System (INIS)

Healy, J.W.; Rodgers, J.C.

1978-10-01

A preliminary study was made of the potential radiation exposures to people from radium-226 contamination in the soil in order to provide guidance on limits to be applied in decontaminating land. Pathways included were inhalation of radium from resuspension; ingestion of radium with foods; external gamma radiation from radium daughters; inhalation of radon and daughter, both in the open air and in houses; and the intake of 210 Pb and 210 Po from both inhalation and ingestion. The depth of the contaminated layer is of importance for external exposure and especially for radon emanation. The most limiting pathway was found to be emanation of the radon into buildings with limiting values comparable to those found naturally in many areas

Inhalation hazards from machining beryllium metal

International Nuclear Information System (INIS)

Hoover, M.D.; Finch, G.L.; Mewhinney, J.A.; Eidson, A.F.

1987-01-01

Beryllium metal has special nuclear and structural properties that make it useful for applications in fission and fusion reactor designs. Unfortunately, concerns for its toxicity have made designers wary of using beryllium metal. The work being reported here was undertaken to characterize the aerosols produced by two very common operations performed during preparation or modification of components for use in reactor systems: sawing and milling of beryllium metal. The study also covered beryllium metal alloys to allow comparison. Information from this study is to enable better assessments of the risk of using beryllium metal in reactor designs

X-ray and radium gamma radiation injuries

International Nuclear Information System (INIS)

Fokkema, R.E.

1993-05-01

During the period 1896-1939 a number of maxima could be distinguished in the incidence of X-ray and radium gamma ray injuries in patients. An explanation for these fluctuations is investigated in this study. The first distinguishable maximum in the number of reported cases of X-ray injuries can be found in the period 1896-1897 and mainly concerns skin lesions, caused by the lack of shielding and ignorance of the effects. In the period 1904-1905 there was once again an apparent prevalence of radiation injuries to patients. After 1905 the incidence of radiation injuries decreased due to a wider use of dosimetric methods. The third phase of increased injuries may be subdivided into three components. In diagnostic roentgenology from 1896 to 1926 a number of causes of roentgen burns persisted: multiple or long exposures, the use of a short focus-skin-distance and a lack of suitable dosimetric methods. The reduction of complications after 1923 can be attributed to several factors: systematic training of physics who wished to become roentgenologists, greater care of doctors, the use of an alternative method of radiotherapy according to Coutard's method, the introduction of dosimetry with ionization chambers (after 1924), the consensus reached over the roentgen as a unit of applied dosage (in 1928), and the introduction of absorption curves for radiation quality (in 1933). Around 1920 a high complication rate arose as a result of exposure to radiation emitted by radium. In 1922 the first reliable radium dosimetry method came available. This applied to external radium therapy by regular shaped applicators. After 1938 reliable dosimetry was achieved in the field of interstitial radium therapy (brachytherapy). Injuries from radium therapy, however, persisted till about 1940, caused not only by the delayed availability of radium dosimetry, but also to the use of radium therapy by poorly trained radium therapists. 28 figs., 5 tabs

Safe waste management practices in beryllium facilities

International Nuclear Information System (INIS)

Bhat, P.N.; Soundararajan, S.; Sharma, D.N.

2012-01-01

Beryllium, an element with the atomic symbol Be, atomic number 4, has very high stiffness to weight ratio and low density. It has good electrical conductive properties with low coefficient of thermal expansion. These properties make the metal beryllium very useful in varied technological endeavours, However, beryllium is recognised as one of the most toxic metals. Revelation of toxic effects of beryllium resulted in institution of stringent health and safety practices in beryllium handling facilities. The waste generated in such facilities may contain traces of beryllium. Any such waste should be treated as toxic waste and suitable safe waste management practices should be adopted. By instituting appropriate waste management practice and through a meticulously incorporated safety measures and continuous surveillance exercised in such facilities, total safety can be ensured. This paper broadly discusses health hazards posed by beryllium and safe methods of management of beryllium bearing wastes. (author)

Beryllium R and D for blanket application

Energy Technology Data Exchange (ETDEWEB)

Dalle Donne, M.; Scaffidi-Argentina, F. [Forschungszentrum Karlsruhe GmbH Technik und Umwelt (Germany). Inst. fuer Neutronenphysik und Reaktortechnik; Longhurst, G.R. [Idaho National Engineering Lab., Idaho Falls (United States); Kawamura, H. [Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment

1998-10-01

The paper describes the main problems and the R and D for the beryllium to be used as neutron multiplier in blankets. As the four ITER partners propose to use beryllium in the form of pebbles for their DEMO relevant blankets (only the Russians consider the porous beryllium option as an alternative) and the ITER breeding blanket will use beryllium pebbles as well, the paper is mainly based on beryllium pebbles. Also the work on the chemical reactivity of fully dense and porous beryllium in contact with water steam is described, due to the safety importance of this point. (orig.) 29 refs.

Beryllium R and D for blanket application

International Nuclear Information System (INIS)

Dalle Donne, M.; Scaffidi-Argentina, F.; Kawamura, H.

1998-01-01

The paper describes the main problems and the R and D for the beryllium to be used as neutron multiplier in blankets. As the four ITER partners propose to use beryllium in the form of pebbles for their DEMO relevant blankets (only the Russians consider the porous beryllium option as an alternative) and the ITER breeding blanket will use beryllium pebbles as well, the paper is mainly based on beryllium pebbles. Also the work on the chemical reactivity of fully dense and porous beryllium in contact with water steam is described, due to the safety importance of this point. (orig.)

Radium issues at Hunters Point Annex

International Nuclear Information System (INIS)

Dean, S.M.

1994-01-01

Radium was a common source of illumination used in numerous instruments and gauges for military equipment prior to 1970. As a result of its many military applications radium 226 is now a principle radionuclide of concern at military base closures sites throughout the United States. This is an overview of the site characterization strategy employed and a potential site remediation technology being considered at a radium contaminated landfill at Hunters Point Annex, a former U.S. Navy shipyard in San Francisco, California

Radithor and the era of mild radium therapy

International Nuclear Information System (INIS)

Macklis, R.M.

1990-01-01

Soon after the discovery of radium, a school of practitioners arose who were interested primarily in the physiological rather than the tumoricidal powers of this new radioactive element. This treatment philosophy was called mild radium therapy and involved the oral or parenteral administration of microgram quantities of radium and its daughter isotopes, often as cures for rheumatic diseases, hypertension, and metabolic disorders. Manufacturers of patent medicines responded to this market by producing a variety of over-the-counter radioactive preparations including pills, elixirs, and salves. One such nostrum was Radithor, a popular and expensive mixture of radium 226 and radium 228 in distilled water. Radithor was advertised as an effective treatment for over 150 endocrinologic diseases, especially lassitude and sexual impotence. Over 400,000 bottles, each containing over 2 muCi (74 kBq) of radium, were apparently marketed and sold worldwide between 1925 and 1930. The death of the Pittsburgh millionaire sportsman Eben M. Byers, who was an avid Radithor user, by radium poisoning in 1932 brought an end to this era and prompted the development of regulatory controls for all radiopharmaceuticals

Association of leukemia with radium groundwater contamination

International Nuclear Information System (INIS)

Lyman, G.H.; Lyman, C.G.; Johnson, W.

1985-01-01

Radiation exposure, including the ingestion of radium, has been causally associated with leukemia in man. Groundwater samples from 27 counties on or near Florida phosphate lands were found to exceed 5 pCi/L total radium in 12.4% of measurements. The incidence of leukemia was greater in those counties with high levels of radium contamination (greater than 10% of the samples contaminated) than in those with low levels of contamination. Rank correlation coefficients of .56 and .45 were observed between the radium contamination level and the incidence of total leukemia and acute myeloid leukemia, respectively. The standardized incidence density ratio for those in high-contamination counties was 1.5 for total leukemia and 2.0 for acute myeloid leukemia. Further investigation is necessary, however, before a causal relationship between groundwater radium content and human leukemia can be established

(Beryllium). Internal Report No. 137, Jan. 15, 1958

International Nuclear Information System (INIS)

Mouret, P.; Rigaud, A.

1959-01-01

After a brief summary of the physical and chemical properties of beryllium, the various chemical treatments which can be applied to beryllium minerals either directly or after a physical enrichment are discussed. These various treatments give either the hydroxide or beryllium salts, from which either beryllium oxide or metallic beryllium can easily be obtained. The purification, analysis and uses of beryllium are also briefly discussed. (author)

Study beryllium microplastic deformation

International Nuclear Information System (INIS)

Papirov, I.I.; Ivantsov, V.I.; Nikolaenko, A.A.; Shokurov, V.S.; Tuzov, Yu.V.

2015-01-01

Microplastic flow characteristics systematically studied for different varieties beryllium. In isostatically pressed beryllium it decreased with increasing particle size of the powder, increasing temperature and increasing the pressing metal purity. High initial values of the limit microelasticity and microflow in some cases are due a high level of internal stresses of thermal origin and over time it can relax slowly. During long-term storage of beryllium materials with high initial resistance values microplastic deformation microflow limit and microflow stress markedly reduced, due mainly to the relaxation of thermal microstrain

Preparation of beryllium hydride

International Nuclear Information System (INIS)

Lowrance, B.R.

1975-01-01

A process is described for the preparation of beryllium hydride which comprises pyrolyzing, while in solution in a solvent inert under the reaction conditions, with respect to reactants and products and at a temperature in the range of about 100 0 to about 200 0 C, sufficient to result in the formation of beryllium hydride, a di-t-alkyl beryllium etherate wherein each tertiary alkyl radical contains from 4 to 20 carbon atoms. The pyrolysis is carried out under an atmosphere inert under the reaction conditions, with respect to reactants and products. (U.S.)

Benchmarking the new JENDL-4.0 library on criticality experiments of a research reactor with oxide LEU (20 w/o) fuel, light water moderator and beryllium reflectors

International Nuclear Information System (INIS)

Liem, Peng Hong; Sembiring, Tagor Malem

2012-01-01

Highlights: ► Benchmark calculations of the new JENDL-4.0 library. ► Thermal research reactor with oxide LEU fuel, H 2 O moderator and Be reflector. ► JENDL-4.0 library shows better C/E values for criticality evaluations. - Abstract: Benchmark calculations of the new JENDL-4.0 library on the criticality experiments of a thermal research reactor with oxide low enriched uranium (LEU, 20 w/o) fuel, light water moderator and beryllium reflector (RSG GAS) have been conducted using a continuous energy Monte Carlo code, MVP-II. The JENDL-4.0 library shows better C/E values compared to the former library JENDL-3.3 and other world-widely used latest libraries (ENDF/B-VII.0 and JEFF-3.1).

Preparation of beryllium hydride

International Nuclear Information System (INIS)

Roberts, C.B.

1975-01-01

A process is described for preparing beryllium hydride by the direct reaction of beryllium borohydride and aluminum hydride trimethylamine adduct. Volatile by-products and unreacted reactants are readily removed from the product mass by sublimation and/or evaporation. (U.S.)

The INEL beryllium multiplication experiment

International Nuclear Information System (INIS)

Smith, J.R.; King, J.J.

1991-03-01

The experiment to measure the multiplication of 14-MeV neutrons in bulk beryllium has been completed. The experiment consists of determining the ratio of 56 Mn activities induced in a large manganese bath by a central 14-MeV neutron source, with and without a beryllium sample surrounding the source. In the manganese bath method a neutron source is placed at the center of a totally-absorbing aqueous solution of MnSo 4 . The capture of neutrons by Mn produces a 56 Mn activity proportional to the emission rate of the source. As applied to the measurement of the multiplication of 14- MeV neutrons in bulk beryllium, the neutron source is a tritium target placed at the end of the drift tube of a small deuteron accelerator. Surrounding the source is a sample chamber. When the sample chamber is empty, the neutrons go directly to the surrounding MnSO 4 solution, and produce a 56 Mn activity proportional to the neutron emission rate. When the chamber contains a beryllium sample, the neutrons first enter the beryllium and multiply through the (n,2n) process. Neutrons escaping from the beryllium enter the bath and produce a 56 Mn activity proportional to the neutron emission rate multiplied by the effective value of the multiplication in bulk beryllium. The ratio of the activities with and without the sample present is proportional to the multiplication value. Detailed calculations of the multiplication and all the systematic effects were made with the Monte Carlo program MCNP, utilizing both the Young and Stewart and the ENDF/B-VI evaluations for beryllium. Both data sets produce multiplication values that are in excellent agreement with the measurements for both raw and corrected values of the multiplication. We conclude that there is not real discrepancy between experimental and calculated values for the multiplication of neutrons in bulk beryllium. 12 figs., 11 tabs., 18 refs

Beryllium minerals - demand strong for miniaturisation

International Nuclear Information System (INIS)

Griffiths, J.

1985-01-01

Beryllium is an essential constituent of over 40 minerals of which two are exploited commercially. Beryl is largely produced in the USSR and China and bertrandite in the U.S.A. Phenacite, from Canada, is also under investigation. The largest extraction plant for the recovery of beryllium in the western world is in Utah, U.S.A. and the company also produces beryllium oxide used in the manufacture of ceramics widely used in the electronics industry and for refractory articles. Beryllium-copper alloys in strip, rod and tube form are produced in the U.S.A., Germany and the U.K. Beryllium ceramics are important because of their high thermal conductivity, electrical insulation, strength and rigidity. The alloys, used as electric connectors, microswitch contacts are important for their high suitability for miniaturisation. The future growth potential for the beryllium industry is in the automotive industries in Europe and Japan. (U.K.)

Study of the radium sorption/desorption on goethite

International Nuclear Information System (INIS)

Bassot, S.; Stammose, D.; Mallet, C.; Lefebvre, C.; Ferreux, J.-M.

2000-01-01

The oxi-hydroxides, present at trace level in uranium mill tailings, are responsible of about 70% of the 226 radium sorption, half being fixed on crystallized forms. This radionuclide (half time=1622y), present at high level (50 to 100kBq.kg -1 ), can be released in groundwater, involving a possible contamination of the food chain (actual concentration limit=0.37Bq.1 -1 ). So, it is very important to point out the mechanisms of the radium sorption/desorption on crystallized oxi-hydroxides as a function of chemical conditions of the system. The radium sorption on synthetic goethite α-FeOOH has been studied as a function of contact time, initial radium activity, pH, sodium and calcium concentrations. The results show that, after one hour of contact time (necessary to reach equilibrium), the radium sorption increases widely in a pH range 6-7. The increase of Na + concentration is without influence on the radium sorption, indicating the low interactions between sodium and surface sites. At the opposite, the presence of calcium in solution decreases widely the radium sorption, that indicates a competition between calcium and radium for the same kind of sorption sites of the oxi-hydroxide surface. The percentage of radium desorbed increases widely with time, from 1 to 120h and becomes constant at a time higher than 120h. This long equilibrium time for desorption in comparison with sorption one can be explain by a local evolution of the sorption sites of the solid, which become less accessible for the solution in contact. (author)

The behaviour of radium in waterways and aquifers

International Nuclear Information System (INIS)

1984-01-01

The Coordinated Research Program was designed to develop systematic information on the form and movement of radium in water under a range of environmental conditions. The final report contains: a) Selection and standardization of methods for determination of radium in water; b) The distribution of soluble and insoluble radium in natural waters, affected by mining or milling operations; c) The factors affecting the leaching rate from ore heaps and tailings piles; d) The uptake of radium by biological systems, especially those which form part of man's food chain. This information being of great value to those authorities responsible for assessing the consequences of radium releases to water and to those responsible for setting discharge limits

Factors affecting radium removal using mixed iron-manganese oxides

International Nuclear Information System (INIS)

Mott, H.V. Singh, S.; Kondapally, V.R.

1993-01-01

Batch experiments confirmed that sorption of radium by a mixed iron-manganese oxide solid phase shows promise for treating radium-contaminated water. The capacities of these mixed oxides for sorption of radium depend on the composition of the solid phase, the pH of the aqueous solution, and the presence of competing cations. The removal of the oxide-radium complexes from aqueous suspension by manganese greensand filtration was also investigated. It was found that influent radium concentrations of 100 pCi/L were reduced to 2--9 pCi/L by this process. Additional study of the fate of radium in manganese greensand filters is recommended before this procedure is used for drinking water treatment

Factors affecting radium removal using mixed iron-manganese oxides

Energy Technology Data Exchange (ETDEWEB)

Mott, H.V. Singh, S.; Kondapally, V.R. (South Dakota School of Mines and Technology, Rapid City, SD (United States))

1993-10-01

Batch experiments confirmed that sorption of radium by a mixed iron-manganese oxide solid phase shows promise for treating radium-contaminated water. The capacities of these mixed oxides for sorption of radium depend on the composition of the solid phase, the pH of the aqueous solution, and the presence of competing cations. The removal of the oxide-radium complexes from aqueous suspension by manganese greensand filtration was also investigated. It was found that influent radium concentrations of 100 pCi/L were reduced to 2--9 pCi/L by this process. Additional study of the fate of radium in manganese greensand filters is recommended before this procedure is used for drinking water treatment.

Conditioning experience for spent radium sources

International Nuclear Information System (INIS)

Kang, I. S.; Shon, J. S.; Kim, K. J.; Min, D. K.

2001-01-01

In order to avoid accidents that could be resulted from improper storage of spent radium sources, it is necessary to condition and store them safely. The program for safe conditioning of spent radium sources by IAEA has been established to assist the developing countries. The main object of this paper is to apply the technology that was adapted by IAEA for the conditioning the national inventory of Ra-226 sources in member states, as a part of IAEA's project with the Korean expert team. This paper is the result that the Korean expert team carried out spent radium conditioning, under the project title 'Radium Conditioning in Myanmar(INT4131-06646C)'. The whole inventory of spent radium sources 1,429.5mCi, was safely conditioned by the Korean expert team according to the manual under the supervision of IAEA's technical officer and the control of Myanmar authority on behalf of Myanmar. These sources were encapsuled and welded into 27 small capsules and 3 large capsules, and conditioned in 3 lead shields, producing 3 concrete-shielded drums. The inventories were distributed into 3 shielding devices, holding 500mCi, 459.5mCi, and 470mCi

Radium removal from Australian spa waters

International Nuclear Information System (INIS)

Dickson, B.L.; Meakins, R.L.; Bland, C.J.

1982-01-01

The dissolved radium content of some mineral spring waters in Victoria and Queensland has been found to exceed the maximum permissible concentration in drinking water. Activities in excess of 40 pCi/1 were measured in some bottles. Studies revealed that the dissolved radium content decreased markedly if the spring water was aerated and filtered prior to bottling. The sediment removed contained ferric hydroxide which is a natural scavenging agent for radium. The formation of such sediments in storage tanks and their removal prior to bottling may create a possible radiation hazard

Beryllium. Its minerals. Pt. 1

International Nuclear Information System (INIS)

Lires, O.A.; Delfino, C.A.; Botbol, J.

1990-01-01

With this work a series of reports begins, under the generic name 'Beryllium', related to several aspects of beryllium technology. The target is to update, with critical sense, current bibliographic material in order to be used in further applications. Some of the most important beryllium ores, the Argentine emplacement of their deposits and world occurrence are described. Argentine and world production, resources and reserves are indicated here as well. (Author) [es

Method for hot pressing beryllium oxide articles

Science.gov (United States)

Ballard, Ambrose H.; Godfrey, Jr., Thomas G.; Mowery, Erb H.

1988-01-01

The hot pressing of beryllium oxide powder into high density compacts with little or no density gradients is achieved by employing a homogeneous blend of beryllium oxide powder with a lithium oxide sintering agent. The lithium oxide sintering agent is uniformly dispersed throughout the beryllium oxide powder by mixing lithium hydroxide in an aqueous solution with beryllium oxide powder. The lithium hydroxide is converted in situ to lithium carbonate by contacting or flooding the beryllium oxide-lithium hydroxide blend with a stream of carbon dioxide. The lithium carbonate is converted to lithium oxide while remaining fixed to the beryllium oxide particles during the hot pressing step to assure uniform density throughout the compact.

Belgian research on fusion beryllium waste

International Nuclear Information System (INIS)

Druyts, F.; Mallants, D.; Sillen, X.; Iseghem, P. Van

2004-01-01

Future fusion power plants will generate important quantities of neutron irradiated beryllium. Although recycling is the preferred management option for this waste, this may not be technically feasible for all of the beryllium, because of its radiological characteristics. Therefore, at SCK·CEN, we initiated a research programme aimed at studying aspects of the disposal of fusion beryllium, including waste characterisation, waste acceptance criteria, conditioning methods, and performance assessment. One of the main issues to be resolved is the development of fusion-specific waste acceptance criteria for surface or deep geological disposal, in particular with regard to the tritium content. In case disposal is the only solution, critical nuclides can be immobilised by conditioning the waste. As a first approach to immobilising beryllium waste, we investigated the vitrification of beryllium. Corrosion tests were performed on both metallic and vitrified beryllium to provide source data for performance assessment. Finally, a first step in performance assessment was undertaken. (author)

Cancer incidence after nasopharyngeal radium irradiation

NARCIS (Netherlands)

Ronckers, Cécile M.; van Leeuwen, Flora E.; Hayes, Richard B.; Verduijn, Pieter G.; Stovall, Marilyn; Land, Charles E.

2002-01-01

From 1940 until 1970, nasopharyngeal radium irradiation was used to treat children and military personnel suffering from Eustachian tube failure attributable to local lymphoid hyperplasia. We studied cancer incidence in a cohort of 4339 Dutch patients treated with nasopharyngeal radium irradiation,

Potential exposures and risks from beryllium-containing products.

Science.gov (United States)

Willis, Henry H; Florig, H Keith

2002-10-01

Beryllium is the strongest of the lightweight metals. Used primarily in military applications prior to the end of the Cold War, beryllium is finding new applications in many commercial products, including computers, telecommunication equipment, and consumer and automotive electronics. The use of beryllium in nondefense consumer applications is of concern because beryllium is toxic. Inhalation of beryllium dust or vapor causes a chronic lung disease in some individuals at concentrations as low as 0.01 microg/m3 in air. As beryllium enters wider commerce, it is prudent to ask what risks this might present to the general public and to workers downstream of the beryllium materials industry. We address this question by evaluating the potential for beryllium exposure from the manufacturing, use, recycle, and disposal of beryllium-containing products. Combining a market study with a qualitative exposure analysis, we determine which beryllium applications and life cycle phases have the largest exposure potential. Our analysis suggests that use and maintenance of the most common types of beryllium-containing products do not result in any obvious exposures of concern, and that maintenance activities result in greater exposures than product use. Product disposal has potential to present significant individual risks, but uncertainties concerning current and future routes of product disposal make it difficult to be definitive. Overall, additional exposure and dose-response data are needed to evaluate both the health significance of many exposure scenarios, and the adequacy of existing regulations to protect workers and the public. Although public exposures to beryllium and public awareness and concern regarding beryllium risks are currently low, beryllium risks have psychometric qualities that may lead to rapidly heightened public concern.

Investigations of the ternary system beryllium-carbon-tungsten and analyses of beryllium on carbon surfaces; Untersuchung des ternaeren Systems Beryllium-Kohlenstoff-Wolfram und Betrachtungen von Beryllium auf Kohlenstoffoberflaechen

Energy Technology Data Exchange (ETDEWEB)

Kost, Florian

2009-05-25

Beryllium, carbon and tungsten are planned to be used as first wall materials in the future fusion reactor ITER. The aim of this work is a characterization of mixed material formation induced by thermal load. To this end, model systems (layers) were prepared and investigated, which give insight into the basic physical and chemical concepts. Before investigating ternary systems, the first step was to analyze the binary systems Be/C and Be/W (bottom-up approach), where the differences between the substrates PG (pyrolytic graphite) and HOPG (highly oriented pyrolytic graphite) were of special interest. Particularly X-ray photoelectron spectroscopy (XPS), low energy ion scattering (ISS) and Rutherford backscattering spectroscopy (RBS) were used as analysis methods. Beryllium evaporated on carbon shows an island growth mode, whereas a closed layer can be assumed for layer thicknesses above 0.7 nm. Annealing of the Be/C system induces Be{sub 2}C island formation for T{>=}770 K. At high temperatures (T{>=}1170 K), beryllium carbide dissociates, resulting in (metallic) beryllium desorption. For HOPG, carbide formation starts at higher temperatures compared to PG. Activation energies for the diffusion processes were determined by analyzing the decreasing beryllium amount versus annealing time. Surface morphologies were characterized using angle-resolved XPS (ARXPS) and atomic force microscopy (AFM). Experiments were performed to study processes in the Be/W system in the temperature range from 570 to 1270 K. Be{sub 2}W formation starts at 670 K, a complete loss of Be{sub 2}W is observed at 1170 K due to dissociation (and subsequent beryllium desorption). Regarding ternary systems, particularly Be/C/W and C/Be/W were investigated, attaching importance to layer thickness (reservoir) variations. At room temperature, Be{sub 2}C, W{sub 2}C, WC and Be{sub 2}W formation at the respective interfaces was observed. Further Be{sub 2}C is forming with increasing annealing temperatures

Radium in Humans: A Review of U.S. Studies.

Science.gov (United States)

Rowland, R. E.

1994-09-01

This document was originally conceived as a description of the radium studies that took place at Argonne National Laboratory. It soon became evident, however, that to document the widespread use of radium, a brief review of the application of radium in medicine and in the US dial painting industry is required. Further, because the Argonne studies were not the only such efforts, brief overviews of the other radium programs are included. Even so, much material has been omitted. The extensive references included will allow the interested reader to find additional information. The effects of internally deposited radium in humans have been studied in this country for more than 75 years. Some 2,400 subjects have had their body contents of radium measured, and a majority of them have been followed for most of their adult lives, to understand and quantify the effects of radium. Many more individuals acquired radium internally but were never measured. Some of this group have been located and followed until death; in these cases the cause of death is known without a body content measurement. As a consequence of the efforts made to locate, measure, and follow exposed individuals, a great deal of information about the effects of radium is available. Nevertheless, great gaps remain in the knowledge of radium toxicity. The Argonne study is the largest every undertaken of the effects on humans of an internally deposited radioelement, in which the insult has been quantitated by actual measurements of the retained radioisotope. The study has now been terminated, even though more than 1,000 subjects with measured radium burdens are still alive. This document is written as a brief summary of current knowledge accumulated in this incomplete study.

Radium in humans: A review of U.S. studies

International Nuclear Information System (INIS)

Rowland, R.E.

1995-01-01

This document was originally conceived as a description of the radium studies that took place at Argonne National Laboratory. It soon became evident, however, that to document the widespread use of radium, a brief review of the application of radium in medicine and in the US dial painting industry is required. Further, because the Argonne studies were not the only such efforts, brief overviews of the other radium programs are included. Even so, much material has been omitted. The extensive references included will allow the interested reader to find additional information. The effects of internally deposited radium in humans have been studied in this country for more than 75 years. Some 2,400 subjects have had their body contents of radium measured, and a majority of them have been followed for most of their adult lives, to understand and quantify the effects of radium. Many more individuals acquired radium internally but were never measured. Some of this group have been located and followed until death; in these cases the cause of death is known without a body content measurement. As a consequence of the efforts made to locate, measure, and follow exposed individuals, a great deal of information about the effects of radium is available. Nevertheless, great gaps remain in the knowledge of radium toxicity. The Argonne study is the largest every undertaken of the effects on humans of an internally deposited radioelement, in which the insult has been quantitated by actual measurements of the retained radioisotope. The study has now been terminated, even though more than 1,000 subjects with measured radium burdens are still alive. This document is written as a brief summary of current knowledge accumulated in this incomplete study

METHOD OF BRAZING BERYLLIUM

Science.gov (United States)

Hanks, G.S.; Keil, R.W.

1963-05-21

A process is described for brazing beryllium metal parts by coating the beryllium with silver (65- 75 wt%)-aluminum alloy using a lithium fluoride (50 wt%)-lithium chloride flux, and heating the coated joint to a temperature of about 700 un. Concent 85% C for about 10 minutes. (AEC)

Effect of duration of exposure to RaCl2 and a radium apatite from freshwater mussels on intestinal transport and bone deposition of radium

International Nuclear Information System (INIS)

Domel, R.U.; Beal, A.M.

1997-01-01

Natural leaching of uranium ore bodies can result in 226 Ra pollution of adjacent waterways and consequent incorporation of radium into the food chain. Mining has the potential to augment this effect. In the Magela flood plain, Northern Territory, the freshwater mussel (Velesunio angasi) concentrates radium in its tissues as a phosphate compound. The availability of mussel radium for uptake and tissue incorporation was assessed relative to radium chloride using rats. The results were compared for jejunal transport (in situ in vivo, ligated segment using anaesthetised animals) and feed trial experiments. In addition, the influence of age and duration of dosage (hours in the case of the jejunal transport and weeks in the feed trial studies) were investigated. Mussel radium transport across the jejunum of adults and juveniles (<0.3%) was very small when compared to radium chloride (50% injected dose). The amount of mussel radium available for intestinal uptake in the feed trials was also low (<0.5%) but significant when compared to the uptake of radium chloride (< 1.5%). Incorporation of mussel radium into bone was less than that of radium chloride (p=0.0001) for both adults and juveniles. Extrapolation of the data from the animal model to humans suggests that eating these mussels carries with it only a low risk of exceeding the Annual Limit of Intake (ALI) set for members of the public, even in juveniles

Sanitary-hygienic and ecological aspects of beryllium production

Energy Technology Data Exchange (ETDEWEB)

Dvinskykh, E.M.; Savchuk, V.V.; Sidorov, V.L.; Slobodin, D.B.; Tuzov, Y.V. [Ulba Metallurgical Plant, Ust-Kamenogorsk (Kazakhstan)

1998-01-01

The Report describes An organization of sanitary-hygienic and ecological control of beryllium production at Ulba metallurgical plant. It involves: (1) the consideration of main methods for protection of beryllium production personnel from unhealthy effect of beryllium, (2) main kinds of filters, used in gas purification systems at different process areas, (3) data on beryllium monitoring in water, soil, on equipment. This Report also outlines problems connected with designing devices for a rapid analysis of beryllium in air as well as problems of beryllium production on ecological situation in the town. (author)

Port Radium Canada's Original Radium/Uranium Mine, The Complete Story of Canada's Historic Radium/Uranium Mine, 1932 to 2012 - 13159

Energy Technology Data Exchange (ETDEWEB)

Chambers, Doug; Wiatzka, Gerd [SENES Consultants Limited, 121 Granton Drive, Unit 12, Richmond Hill, ON L4B 3N4 (United States); Brown, Steve [SENES Consultants Limited, 8310 South Valley Highway, Suite 3016, Englewood, Colorado 80112 (United States)

2013-07-01

This paper provides the life story of Canada's original radium/uranium mine. In addition to the history of operations, it discusses the unique and successful approach used to identify the key issues and concerns associated with the former radium, uranium and silver mining property and the activities undertaken to define the remedial actions and subsequent remedial plan. The Port Radium Mine site, situated approximately 275 km north of Yellowknife on the east shore of Great Bear Lake, Northwest Territories, was discovered in 1930 and underground mining began in 1932. The mine operated almost continuously from 1932 to 1982, initially for recovery of radium, then uranium and finally, for recovery of silver. Tailings production totaled an estimated 900,000 tons and 800,000 tons from uranium and silver processing operations respectively. In the early days of mining, Port Radium miners were exposed to radon and associated decay product levels (in Working Level Months of exposure - WLM) hundreds of times greater than modern standards. The experience of the Port Radium miners provides important contribution to understanding the risks from radon. While the uranium mine was originally decommissioned in the early 1960's, to the standards of the day, the community of Deline (formerly Fort Franklin) had concerns about residual contamination at the mine site and the potential effects arising from use of traditional lands. The Deline people were also concerned about the possible risks to Deline Dene arising from their work as ore carriers. In the late 1990's, the community of Deline brought these concerns to national attention and consequently, the Government of Canada and the community of Deline agreed to move forward in a collaborative manner to address these concerns. The approach agreed to was to establish the Canada-Deline Uranium Table (CDUT) to provide a joint process by which the people of Deline could have their concerns expressed and addressed. A great

Beryllium for fusion application - recent results

International Nuclear Information System (INIS)

Khomutov, A.; Barabash, V.; Chakin, V.; Chernov, V.; Davydov, D.; Gorokhov, V.; Kawamura, H.; Kolbasov, B.; Kupriyanov, I.; Longhurst, G.; Scaffidi-Argentina, F.; Shestakov, V.

2002-01-01

The main issues for the application of beryllium in fusion reactors are analyzed taking into account the latest results since the ICFRM-9 (Colorado, USA, October 1999) and presented at 5th IEA Be Workshop (10-12 October 2001, Moscow Russia). Considerable progress has been made recently in understanding the problems connected with the selection of the beryllium grades for different applications, characterization of the beryllium at relevant operational conditions (irradiation effects, thermal fatigue, etc.), and development of required manufacturing technologies. The key remaining problems related to the application of beryllium as an armour in near-term fusion reactors (e.g. ITER) are discussed. The features of the application of beryllium and beryllides as a neutron multiplier in the breeder blanket for power reactors (e.g. DEMO) in pebble-bed form are described

Beryllium for fusion application - recent results

Science.gov (United States)

Khomutov, A.; Barabash, V.; Chakin, V.; Chernov, V.; Davydov, D.; Gorokhov, V.; Kawamura, H.; Kolbasov, B.; Kupriyanov, I.; Longhurst, G.; Scaffidi-Argentina, F.; Shestakov, V.

2002-12-01

The main issues for the application of beryllium in fusion reactors are analyzed taking into account the latest results since the ICFRM-9 (Colorado, USA, October 1999) and presented at 5th IEA Be Workshop (10-12 October 2001, Moscow Russia). Considerable progress has been made recently in understanding the problems connected with the selection of the beryllium grades for different applications, characterization of the beryllium at relevant operational conditions (irradiation effects, thermal fatigue, etc.), and development of required manufacturing technologies. The key remaining problems related to the application of beryllium as an armour in near-term fusion reactors (e.g. ITER) are discussed. The features of the application of beryllium and beryllides as a neutron multiplier in the breeder blanket for power reactors (e.g. DEMO) in pebble-bed form are described.

The behaviour of radium in soil and in uranium mine-tailings

International Nuclear Information System (INIS)

Shoesmith, D.W.

1984-09-01

The existence of a number of historical wastes has prompted the need to develop a disposal strategy for material contaminated with radium-226. This report reviews the pertinent radiological and chemical properties of radium. Chemical factors that determine the mobility of radium in soil/groundwater environments are discussed. The mineralogy of mine tailings and attempts to leach them are reviewed. Radium levels in leached residues are compared to the standards for radium levels, and realistic targets are suggested for leaching methods. Techniques for scrubbing soil, immobilizing radium and treating wastewater containing radium are reviewed. Recommendations are made for a possible leaching strategy for radium-contaminated soil, and for further research to develop an effective disposal strategy

The nature of beryllium disease

International Nuclear Information System (INIS)

Williams, W.J.

1977-01-01

The increasing use of beryllium in modern industry poses a continuing health hazard with a real risk of producing incapacitating disease and even death. Beryllium and its salts are very toxic, even in small doses and may produce lesions in any organ. The majority of cases follow inhalation and may cause either acute or chronic lung disease. Acute pulmonary disease is a form of chemical pneumonitis while the chronic disease is characterised by the production of granulomas and fibrosis. The skin may be affected with the finding of dermatitis, acute or chronic ulceration. Other organs commonly involved include the liver and kidneys. The pathology of beryllium disease is not specific and diagnosis depends on satisfying the following criteria - history of exposure, consistent clinical, radiographic and pathological finding, presence of beryllium in tissue/fluid and evidence of hypersensitivity. Recent development of 'in vitro' tests of hypersensitivity may prove of value in both diagnosis and prevention of disease. Beryllium disease responds to steroid therapy but the only sure treatment is avoidance of exposure. (author)

Radium in humans: A review of U.S. studies

Energy Technology Data Exchange (ETDEWEB)

Rowland, R.E.

1994-09-01

This document was originally conceived as a compilation of activities at Argonne National Laboratory that were directed toward the study of radium in humans. However, it soon became obvious that this was a very limited approach, because such a compilation would include no background on the widespread uses of radium in industry and in the medical profession, nor would it address the early history of the discovery of the hazards of radium. Such an approach would also ignore contributions to the study of radium effects made at other laboratories. This document now addresses these topics, in order to give an overall picture of what might be called the radium era, that period from the early part of this century, when radium was rapidly exploited as a tool and a medication, to the present time, when radium is not generally used and the study of its effects has been terminated. The appendix to this review lists all of the measured radium cases, a total of 2,403 individuals whose records were in the files at the end of 1990. For each case the route of exposure, the dates of exposure, the years of birth and death, the measured body content, the calculated intake and dose, and the cause of death have been listed. 165 refs.

Beryllium electrodeposition on aluminium cathode from chloride melts

International Nuclear Information System (INIS)

Nichkov, I.F.; Novikov, E.A.; Serebryakov, G.A.; Kanashin, Yu.P.; Sardyko, G.N.

1980-01-01

Cathodic processes during beryllium deposition on liquid and solid aluminium cathodes are investigated. Mixture of sodium, potassium and beryllium chloride melts served as an lectrolyte. Beryllium ion discharge at the expense of alloy formation takes place at more positive potentials than on an indifferent cathode at low current densities ( in the case of liquid aluminium cathode). Metallographic analysis and measurements of microhardness have shown, that the cathodic product includes two phases: beryllium solid solution in aluminium and metallic beryllium. It is concluded, that aluminium-beryllium alloys with high cathodic yield by current can be obtained by the electrolytic method

Beryllium satellite thrust cone design, manufacture and test

International Nuclear Information System (INIS)

Schneiter, H.; Chandler, D.

1977-01-01

Pre-formed beryllium sheet material has been used in the design, manufacturing and test of a satellite thrust cone structure. Adhesive bonding was used for attachment of aluminium flanges and conical segment lap strips. Difficulties in beryllium structure design such as incompatibilities with aluminium and handling problems are discussed. Testing to optimize beryllium-beryllium and beryllium-aluminium adhesive bonds is described. The completed thrust cone assembly has been subjected to static load testing and the results are presented. A summary of the relative merits of the use of beryllium in satellite structures is given with recommendations for future users. (author)

Control of beryllium powder at a DOE facility

International Nuclear Information System (INIS)

Langner, G.C.; Creek, K.L.; Castro, R.G.

1997-01-01

Beryllium is contained in a number of domestic and national defense items. Although many items might contain beryllium in some manner, few people need worry about the adverse effects caused by exposure to beryllium because it is the inhalable form of beryllium that is most toxic. Chronic beryllium disease (CBD), a granulomas and fibrotic lung disease with long latency, can be developed after inhalation exposures to beryllium. It is a progressive, debilitating lung disease. Its occurrence in those exposed to beryllium has been difficult to predict because some people seem to react to low concentration exposures whereas others do not react to high concentration exposures. Onset of the disease frequently occurs between 15 to 20 years after exposure begins. Some people develop the disease after many years of low concentration exposures but others do not develop CBD even though beryllium is shown to be present in lungs and urine. Conclusions based on these experiences are that their is some immunological dependence of developing CBD in about 3--4% of the exposed population, but the exact mechanism involved has not yet been identified. Acute beryllium disease can occur after a single exposure to a concentration of greater than 0.100 mg/m3 (inhalation exposure); it is characterized by the development of chemical pneumoconiosis, a respiratory disease. The acute effect of skin contact is a dermatitis characterized by itching and reddened, elevated, or fluid-accumulated lesions which appear particularly on the exposed surfaces of the body, especially the face, neck, arms, and hands. Small particles of beryllium that enter breaks in the skin can lead to the development of granulomas and/or open sores that do not heal until the beryllium has been removed. Our interest is only airborne beryllium, which is found in areas that machine or produce beryllium

Radium and uranium concentrations and associated hydrogeochemistry in ground water in southwestern Pueblo County, Colorado

Science.gov (United States)

Felmlee, J. Karen; Cadigan, Robert Allen

1979-01-01

Radium and uranium concentrations in water from 37 wells tapping the aquifer system of the Dakota Sandstone and Purgatoire Formation in southwestern Pueblo County, Colorado, have a wide range of values and define several areas of high radioactivity in the ground water. Radium ranges from 0.3 to 420 picocuries per liter and has a median value of 8.8, and uranium ranges from 0.02 to 180 micrograms per liter and has a median value of 2.4. Radon concentrations, measured in 32 of the 37 wells, range from less than 100 picocuries per liter to as much as 27,000 and have a median value of 580. Relationships among the radioactive elements and 28 other geochemical parameters were studied by using correlation coefficients and R-mode factor analysis. Five factor groups were determined to represent major influences on water chemistry: (1) short-term solution reactions, (2) oxidation reactions, (3) hydrolysis reactions, (4) uranium distribution, and (5) long-term solution reactions. Uranium concentrations are most strongly influenced by oxidation reactions but also are affected by solution reactions and distribution of uranium in the rocks of the aquifer system. Radon and radium concentrations are mostly controlled by uranium distribution; radium also shows a moderate negative relationship with oxidation. To explain the statistical and spatial relationships among the parameters, a model was developed involving the selective leaching of uranium-bearing phases and metal sulfides which occur in discontinuous zones in sandstone and shale. When reducing conditions prevail, uranium is immobile, but radium can be taken into solution. When faults and associated fractured rocks allow oxidizing conditions to dominate, uranium can be taken into solution; radium can also be taken into solution, or it may become immobilized by coprecipitation with iron and manganese oxides or with barite. Several areas within the study area are discussed in terms of the model.

Placement of radium/barium sludges in tailings areas

International Nuclear Information System (INIS)

Murphy, K.L.; Multamaki, G.E.

1980-01-01

Currently radium is removed from uranium mining and milling effluents by the addition of barium chloride to precipitate the radium as radium/barium sulphate. The precipitate is allowed to settle in sedimentation basins prior to discharge of the effluent. The sedimentation basins are not suitable for final disposal of the sludge, and placement of the sludges in the tailings area has been proposed. The geochemical environment of fresh tailings areas was characterized as an acidic, oxidized surface zone underlain by an alkaline, reduced zone comprising the rest of the tailings. The quantity of sludge produced was estimated to be small relative to the quantity of tailings, and therefor a relatively small amount of radium would be added to the tailings disposal area by the addition of sludge. To confirm whether sludge addition affected radionuclide solubilization, laboratory leaching tests were conducted on slurries of acid leach tailings, and sludge-tailings mixtures. Radium in the (Ra,Ba)SO 4 sludge was at least as stable as radium in the tailings, and the sludge was able to absorb radium released from the tailings. The addition of sludge did not affect uranium and thorium solubilization. From these results it appears that the placement of sludge in tailings areas would not adversely affect the stability of radionuclides in the tailings or sludge. (auth)

Bone sarcoma in humans induced by radium: A threshold response?

International Nuclear Information System (INIS)

Rowland, R.E.

1996-01-01

The radium 226 and radium 228 have induced malignancies in the skeleton (primarily bone sarcomas) of humans. They have also induced carcinomas in the paranasal sinuses and mastoid air cells. There is no evidence that any leukemias or any other solid cancers have been induced by internally deposited radium. This paper discuses a study conducted on the dial painter population. This study made a concerted effort to verify, for each of the measured radium cases, the published values of the skeletal dose and the initial intake of radium. These were derived from body content measurements made some 40 years after the radium intake. Corrections to the assumed radium retention function resulted in a considerable number of dose changes. These changes have changed the shape of the dose response function. It now appears that the induction of bone sarcomas is a threshold process

Recycling radium

International Nuclear Information System (INIS)

Blair, J.A.

1997-01-01

The Technology Programs Department of Fluor Daniel Fernald investigated alternatives for dealing with the World's largest concentrated supply of radium, the K-65 silos at Fernald, the United States Department of Energy's (DOE) former uranium processing facility near Cincinnati, Ohio. These two silos contain nearly 3,770 curies (by definition 3,770 grams) primarily of Ra-226 (T 1/2 = 1600 a) within 10,000 metric tons of material. Material contents of the silos were to be vitrified according to a Record of Decision (ROD) between the DOE and the United States Environmental Protection Agency (EPA). Because of cost considerations, that alternative must be reconsidered. Research showed that although Ra-226 had come mostly into disfavor as a therapeutic agent for cancer, isotopes derived from the neutron bombardment of pure Ra-226 and radioactive decay of the resulting purified isotopes could be used to good effect. One of these isotopes, bismuth-213 (Bi-213, T 1/2 = 45.6 m), is being used in clinical trials against acute myelogenous leukemia. The isotope is attached to an antibody that seeks out cancer cells. Because alpha particles dissipate most of their energy within the space of one or a few cells, virtually all the surrounding healthy tissue remains unharmed. Because of the short half life, waste disposal is no problem. Because of past policies, radium for feedstock is difficult to find. A new policy is needed in the United States acknowledging radium's value for feedstock while continuing to control its health and environmental consequences

Controls on radium transport by adsorption to iron minerals

Science.gov (United States)

Chen, M.; Wang, T.; Kocar, B. D.

2015-12-01

Radium is a naturally occurring radioactive metal found in many subsurface environments. Radium isotopes are generated by uranium and thorium decay, and are particularly abundant within groundwaters where minimal porewater flux leads to accumulation. These isotopes are used as natural tracers for estimating submarine groundwater discharge (SGD) [1], allowing for large scale estimation of GW fluxes into and out of the ocean [2]. They also represent a substantial hazard in wastewater produced after hydraulic fracturing for natural gas extraction [3], resulting in a significant risk of environmental release to surface and near-surface waters, and increased cost for water treatment or disposal. Adsorption to mineral surfaces represents a dominant pathway of radium retention in subsurface environments. For SGD studies, adsorption processes impact estimates of GW fluxes, while in hydraulic fracturing, radium adsorption to aquifer solids mediates wastewater radium activities. Analysis of past sorption studies revealed large variability in partition coefficients [4], while examination of radium adsorption kinetics and surface complexation have only recently started [5]. Accordingly, we present the results of sorption and column experiments of radium with a suite of iron minerals representative of those found within deep saline and near-surface (freshwater) aquifers, and evaluate impacts of varying salinity solutions through artificial waters. Further, we explore the impacts of pyrite oxidation and ferrihydrite transformation to other iron-bearing secondary minerals on the transport and retention of radium. These results will provide critical information on the mineralogical controls on radium retention in subsurface environments, and will therefore improve predictions of radium groundwater transport in natural and contaminated systems. [1] Charette, M.A., Buesseler, K.O. & Andrews, J.E., Limnol. Oceanogr. (2001). [2] Moore, W.S., Ann. Rev. Mar. Sci. (2010). [3] Vengosh, A

Radium 226 in the deep north-eastern Atlantic Ocean

International Nuclear Information System (INIS)

Rhein, M.

1986-01-01

With reference to the distribution of radium-226 in the western equatorial and north-eastern deep Atlantic Ocean it was possible to establish structures in the correlations of radium-226 to its chemical homologue Ba and dissolved SiO 2 . An 11-box model of the deep Atlantic Ocean was used to obtain information on the size of the radium-226 and Ba sources. The soil source derives mainly from the dissolution of barite. For the first time, an evaluation of the radium-226 flow resulting from the dissolution of particulate matter is presented. The box model and the radium-226 concentrations measured put down the value as 23-46·10 -21 mol/m 2 s. (DG) [de

Research of beryllium safety issues

International Nuclear Information System (INIS)

Longhurst, G.R.; Anderl, R.A.; Dolan, T.J.; Hankins, M.R.; Pawelko, R.J.

1993-01-01

Beryllium has been identified as a leading contender for the plasma-facing material in ITER. Its use has some obvious advantages, but there are also a number of safety concerns associated with it. The Idaho National Engineering Laboratory (INEL) has undertaken a number of studies to help resolve some of these issues. One issue is the response of beryllium to neutron irradiation. We have tested samples irradiated in the Advanced Test Reactor (ATR) and are currently preparing to make measurements of the change in mechanical properties of beryllium samples irradiated at elevated temperatures in the Fast Flux Test Facility (FFTF) and the Experimental Breeder Reactor II (EBR-II) at the INEL. Mechanical tests will be conducted at the irradiation temperatures of 375-550 C. Other experiments address permeation and retention of implanted tritium in plasma-sprayed beryllium. In one test the porosity of the material allowed 0.12% of implanted ions and 0.17% of atoms from background gas pressure to pass through the foil with essentially no delay. For comparison, similar tests on fully dense hot-rolled, vacuum melted or sintered powder foils of high purity beryllium showed only 0.001% of implanting ions to pass through the foil, and then only after a delay of several hours. None of the molecular gas appeared to permeate these latter targets. An implication is that plasma-sprayed beryllium may substantially enhance recycling of tritium to the plasma provided it is affixed to a relatively impermeable substrate. (orig.)

Offshoots from beryllium development programme

International Nuclear Information System (INIS)

Sharma, B.P.; Sinha, P.K.

1995-01-01

The paper briefly presents extraction and processing of beryllium metal as practiced in the beryllium facilities at Turbhe, New Bombay. These facilities have been set up to meet the indigenous requirements of the metal in space and nuclear science programmes. As offshoot of this beryllium development programme has been the development of a number of pyro and powder metallurgical equipment. Indigenous development of these pieces of equipment has been a professionally rewarding experience. Efforts are now on to promote these equipment for industrial use. (author). 6 refs., 6 figs., 2 tabs

Fluorimetric method for determination of Beryllium

International Nuclear Information System (INIS)

Sparacino, N.; Sabbioneda, S.

1996-10-01

The old fluorimetric method for the determination of Beryllium, based essentially on the fluorescence of the Beryllium-Morine complex in a strongly alkaline solution, is still competitive and stands the comparison with more modern methods or at least three reasons: in the presence of solid or gaseous samples (powders), the times necessary to finalize an analytic determination are comparable since the stage of the process which lasts the longest is the mineralization of the solid particles containing Beryllium, the cost of a good fluorimeter is by far Inferior to the cost, e. g., of an Emission Spectrophotometer provided with ICP torch and magnets for exploiting the Zeeman effect and of an Atomic absorption Spectrophotometer provided with Graphite furnace; it is possible to determine, fluorimetrically, rather small Beryllium levels (about 30 ng of Beryllium/sample), this potentiality is more than sufficient to guarantee the respect of all the work safety and hygiene rules now in force. The study which is the subject of this publication is designed to the analysis procedure which allows one to reach good results in the determination of Beryllium, chiefly through the control and measurement of the interference effect due to the presence of some metals which might accompany the environmental samples of workshops and laboratories where Beryllium is handled, either at the pure state or in its alloys. The results obtained satisfactorily point out the merits and limits of this analytic procedure

Effect of duration of exposure to RaCl{sub 2} and a radium apatite from freshwater mussels on intestinal transport and bone deposition of radium

Energy Technology Data Exchange (ETDEWEB)

Domel, R U [Australian Nuclear Science and Technology Organsiation, Lucas Heights, NSW (Australia). Environment Division; Beal, A M [University of New South Wales, NSW (Australia). Biological Science

1997-10-01

Natural leaching of uranium ore bodies can result in {sup 226}Ra pollution of adjacent waterways and consequent incorporation of radium into the food chain. Mining has the potential to augment this effect. In the Magela flood plain, Northern Territory, the freshwater mussel (Velesunio angasi) concentrates radium in its tissues as a phosphate compound. The availability of mussel radium for uptake and tissue incorporation was assessed relative to radium chloride using rats. The results were compared for jejunal transport (in situ in vivo, ligated segment using anaesthetised animals) and feed trial experiments. In addition, the influence of age and duration of dosage (hours in the case of the jejunal transport and weeks in the feed trial studies) were investigated. Mussel radium transport across the jejunum of adults and juveniles (<0.3%) was very small when compared to radium chloride (50% injected dose). The amount of mussel radium available for intestinal uptake in the feed trials was also low (<0.5%) but significant when compared to the uptake of radium chloride (< 1.5%). Incorporation of mussel radium into bone was less than that of radium chloride (p=0.0001) for both adults and juveniles. Extrapolation of the data from the animal model to humans suggests that eating these mussels carries with it only a low risk of exceeding the Annual Limit of Intake (ALI) set for members of the public, even in juveniles 18 refs., 5 figs.

New Jersey Radium Research Project: final report

International Nuclear Information System (INIS)

Sharpe, W.D.

1979-01-01

Cancers among dead New Jersey subjects were almost three times the expected number. Their radiation experience apparently acted as a generalized carcinogen. Conventional clinical, laboratory and roentgenographic tests neither correlated with calculated radiation exposure nor predicted which subjects subsequently developed cancer. More subjects than expected were deaf and enough of the subjects had increased erythrocyte sedimentation rates and decreased alpha-1 serum globulin levels that both hearing tests and tests of immune competence should be undertaken among asymptomatic exposed populations at regular intervals to see whether these may indicate radiation effects prior to a fatal cancer or blood dyscrasia. If pre-terminal radium-226 burdens validly express total irradiation experience, and past exposure to shorter-lived radium-228 (mesothorium) makes it unlikely that this is so, the distribution of radium osteitis among our subjects suggests that anatomically demonstrable radiation injury occurs in the vast majority of subjects with any radium-226 burden that can be measured above background levels after twenty-five years, and in almost half of those exposed whose measured radium-226 burdens are indistinguishable from background levels. Modification of the occupational exposure standard is recommended

New Jersey Radium Research Project: final report

Energy Technology Data Exchange (ETDEWEB)

Sharpe, W.D.

1979-01-01

Cancers among dead New Jersey subjects were almost three times the expected number. Their radiation experience apparently acted as a generalized carcinogen. Conventional clinical, laboratory and roentgenographic tests neither correlated with calculated radiation exposure nor predicted which subjects subsequently developed cancer. More subjects than expected were deaf and enough of the subjects had increased erythrocyte sedimentation rates and decreased alpha-1 serum globulin levels that both hearing tests and tests of immune competence should be undertaken among asymptomatic exposed populations at regular intervals to see whether these may indicate radiation effects prior to a fatal cancer or blood dyscrasia. If pre-terminal radium-226 burdens validly express total irradiation experience, and past exposure to shorter-lived radium-228 (mesothorium) makes it unlikely that this is so, the distribution of radium osteitis among our subjects suggests that anatomically demonstrable radiation injury occurs in the vast majority of subjects with any radium-226 burden that can be measured above background levels after twenty-five years, and in almost half of those exposed whose measured radium-226 burdens are indistinguishable from background levels. Modification of the occupational exposure standard is recommended. (PCS)

Removal method of radium in mine water by filter sand

International Nuclear Information System (INIS)

Taki, Tomihiro; Naganuma, Masaki

2003-01-01

Trace radium is contained in mine water from the old mine road in Ningyo-Toge Environmental Engineering Center, JNC. We observed that filter sand with hydrated manganese oxide adsorbed radium in the mine water safely for long time. The removal method of radium by filter sand cladding with hydrated manganese oxide was studied. The results showed that radium was removed continuously and last for a long time from mine water with sodium hypochlorite solution by passing through the filter sand cladding with hydrated manganese. Only sodium hypochlorite solution was used. When excess of it was added, residue chlorine was used as chlorine disinfection. Filter sand cladding with hydrated manganese on the market can remove radium in the mine water. The removal efficiency of radium is the same as the radium coprecipitation method added with barium chloride. The cost is much lower than the ordinary methods. Amount of waste decreased to about 1/20 of the coprecipitation method. (S.Y.)

Preparation of beryllium hydride

International Nuclear Information System (INIS)

Bergeron, C.R.; Baker, R.W.

1975-01-01

Beryllium hydride of high bulk density, suitable for use as a component of high-energy fuels, is prepared by the pyrolysis, in solution in an inert solvent, of a ditertiary-alkyl beryllium. An agitator introduces mechanical energy into the reaction system, during the pyrolysis, at the rate of 0.002 to 0.30 horsepower per gallon of reaction mixture. (U.S.)

High-strength beryllium block

International Nuclear Information System (INIS)

Pinto, N.P.; Keith, G.H.

1977-01-01

Beryllium billets hot isopressed using fine powder of high purity have exceptionally attractive properties; average tensile ultimate, 0.2% offset yield strength and elongation are 590 MPa, 430 MPa and 4.0% respectively. Properties are attributed to the fine grain size (about 4.0 μm average diameter) and the relatively low levels of BeO present as fine, well-dispersed particles. Dynamic properties, e.g., fracture toughness, are similar to those of standard grade, high-purity beryllium. The modulus of beryllium is retained to very high stress levels, and the microyield stress or precision elastic limit is higher than for other grades, including instrument grades. Limited data for billets made from normal-purity fine powders show similar room temperature properties. (author)

Use of carriers for to electrodeposited radium 226

International Nuclear Information System (INIS)

Iturbe, J.L.

1991-10-01

The form of the energy distribution of a monoenergetic alpha particle starting from some emitting source of these particles, it depends on the quantity of material that its cross before being detected. Some authors deposit to the radium-226 by means of direct evaporation of the solution on metallic supports, on millipore paper and by electrodeposition. Some other ones place the radium solution in scintillation liquid, to quantify it by this technique. The objective of the present work is using carriers with the same oxidation state of the radium, that is to say of 2 + , for treating to be electrodeposited to the radium-226 with the biggest possible percentage for later use the alpha spectroscopy technique to quantify it. The carriers that have been used until its they are barium and zinc in form of barium chloride, zinc nitrate and zinc sulfate. The first results indicate that with the zinc solution a yield of 40% of electrodeposited radium has been reached. (Author)

Reaction-diffusion modeling of hydrogen in beryllium

Energy Technology Data Exchange (ETDEWEB)

Wensing, Mirko; Matveev, Dmitry; Linsmeier, Christian [Forschungszentrum Juelich GmbH, Institut fuer Energie- und Klimaforschung - Plasmaphysik (Germany)

2016-07-01

Beryllium will be used as first-wall material for the future fusion reactor ITER as well as in the breeding blanket of DEMO. In both cases it is important to understand the mechanisms of hydrogen retention in beryllium. In earlier experiments with beryllium low-energy binding states of hydrogen were observed by thermal desorption spectroscopy (TDS) which are not yet well understood. Two candidates for these states are considered: beryllium-hydride phases within the bulk and surface effects. The retention of deuterium in beryllium is studied by a reaction rate approach using a coupled reaction diffusion system (CRDS)-model relying on ab initio data from density functional theory calculations (DFT). In this contribution we try to assess the influence of surface recombination.

Recommended design correlations for S-65 beryllium

International Nuclear Information System (INIS)

Billone, M.C.

1995-01-01

The properties of tritium and helium behavior in irradiated beryllium are reviewed, along with the thermal-mechanical properties needed for ITER design analysis. Correlations are developed to describe the performance of beryllium in a fusion reactor environment. While this paper focuses on the use of beryllium as a plasma-facing component (PFC) material, the correlations presented here can also be used to describe the performance of beryllium as a neutron multiplier for a tritium breeding blanket. The performance properties for beryllium are subdivided into two categories: properties which do not change with irradiation damage to the bulk of the material; and properties which are degraded by neutron irradiation. The irradiation-independent properties described within are: thermal conductivity, specific heat capacity, thermal expansion, and elastic constants. Irradiation-dependent properties include: yield strength, ultimate tensile strength, plastic tangent modulus, uniform and total tensile elongation, thermal and irradiation-induced creep strength, He-induced swelling and tritium retention/release. The approach taken in developing properties correlations is to describe the behavior of dense, pressed S-65 beryllium -- the material chosen for ITER PFC application -- as a function of temperature. As there are essentially no data on the performance of porous and/or irradiated S-65 beryllium, the degradation of properties with as-fabricated porosity and irradiation are determined from the broad data base on S-200F, as well as other types and grades, and applied to S-65 beryllium by scaling factors. The resulting correlations can be used for Be produced by vacuum hot pressing (VHP) and cold-pressing (CP)/sintering(S)/hot-isostatic-pressing (HIP). The performance of plasma-sprayed beryllium is discussed but not quantified

Radium Adsorption to Iron Bearing Minerals in Variable Salinity Waters

Science.gov (United States)

Chen, M.; Kocar, B. D.

2014-12-01

Radium is a common, naturally occurring radioactive metal found in many subsurface environments. Radium isotopes are a product of natural uranium and thorium decay, and are particularly abundant within groundwaters where minimal flux leads to accumulation within porewaters. Radium has been used as a natural tracer to estimate submarine groundwater discharge (SGD) [1], where the ratios of various radium isotopes are used to estimate total groundwater flux to and from the ocean [2]. Further, it represents a substantial hazard in waste water produced after hydraulic fracturing for natural gas extraction [3], resulting in a significant risk of environmental release and increased cost for water treatment or disposal. Adsorption to mineral surfaces represents a primary pathway of radium retention within subsurface environments. For SGD studies, it is important to understand adsorption processes to correctly estimate GW fluxes, while in hydraulic fracturing, radium adsorption to aquifer solids will mediate the activities of radium within produced water. While some studies of radium adsorption to various minerals have been performed [4], there is a limited understanding of the surface chemistry of radium adsorption, particularly to iron-bearing minerals such as pyrite, goethite and ferrihydrite. Accordingly, we present the results of sorption experiments of radium to a suite of iron-bearing minerals representative of those found within deep saline and near-surface (freshwater) aquifers, and evaluate impacts of varying salinity solutions through the use of artificial groundwater, seawater, and shale formation brine. Further, we explore the impacts of pyrite oxidation and ferrihydrite transformation to other iron-bearing secondary minerals on the retention of radium. This work lays the groundwork for further study of radium use as a tracer for SGD, as well as understanding mechanisms of radium retention and release from deep aquifer materials following hydraulic fracturing

Exposure and genetics increase risk of beryllium sensitisation and chronic beryllium disease in the nuclear weapons industry.

Science.gov (United States)

Van Dyke, Michael V; Martyny, John W; Mroz, Margaret M; Silveira, Lori J; Strand, Matt; Cragle, Donna L; Tankersley, William G; Wells, Susan M; Newman, Lee S; Maier, Lisa A

2011-11-01

Beryllium sensitisation (BeS) and chronic beryllium disease (CBD) are caused by exposure to beryllium with susceptibility affected by at least one well-studied genetic host factor, a glutamic acid residue at position 69 (E69) of the HLA-DPβ chain (DPβE69). However, the nature of the relationship between exposure and carriage of the DPβE69 genotype has not been well studied. The goal of this study was to determine the relationship between DPβE69 and exposure in BeS and CBD. Current and former workers (n=181) from a US nuclear weapons production facility, the Y-12 National Security Complex (Oak Ridge, Tennessee, USA), were enrolled in a case-control study including 35 individuals with BeS and 19 with CBD. HLA-DPB1 genotypes were determined by PCR-SSP. Beryllium exposures were assessed through worker interviews and industrial hygiene assessment of work tasks. After removing the confounding effect of potential beryllium exposure at another facility, multivariate models showed a sixfold (OR 6.06, 95% CI 1.96 to 18.7) increased odds for BeS and CBD combined among DPβE69 carriers and a fourfold (OR 3.98, 95% CI 1.43 to 11.0) increased odds for those exposed over an assigned lifetime-weighted average exposure of 0.1 μg/m(3). Those with both risk factors had higher increased odds (OR 24.1, 95% CI 4.77 to 122). DPβE69 carriage and high exposure to beryllium appear to contribute individually to the development of BeS and CBD. Among workers at a beryllium-using facility, the magnitude of risk associated with either elevated beryllium exposure or carriage of DPβE69 alone appears to be similar.

Case report 361: Radium intoxication with radium-induced osteonecrosis

Energy Technology Data Exchange (ETDEWEB)

Milgram, J.W.; Jasty, M.

1986-03-01

In summary, a male patient was treated with radium chloride for arthritis involving both knees at a time when he had gonococcal urethritis. He was then 20 years of age and was followed until his death 40 years later at the age of 60 years. During that interval this individual, who possessed one of the largest burdens of radium ever recorded in man, developed spontaneous fractures of both femori and one humerus, symptomatic osteonecrosis of both femoral heads, dramatic progressive radiological findings of bone, and finally, a carcinoma of the maxillary sinus which proved to be the cause of his death. Tissue was obtained from both cortical and cancellous bone at four different times during the patient's life and again at post-mortem. Progressive ischemia with abnormal calcification and then necrosis of both bone and bone marrow were demonstrated in the skeletal tissues. The pathological chances are correlated superbly with the roentgenograms in this report.

Some aspects of beryllium disposal in Kazakhstan

International Nuclear Information System (INIS)

Shestakov, V.; Chikhray, Y.; Shakhvorostov, Yr.

2004-01-01

Historically in Kazakhstan all disposals of used beryllium and beryllium wasted materials were stored and recycled at JSC ''Ulba Metallurgical Plant''. Since Ulba Metallurgical Plant (beside beryllium and tantalum production) is one of the world largest complex producers of fuel for nuclear power plants as well it has possibilities, technologies and experience in processing toxic and radioactive wastes related with those productions. At present time only one operating Kazakhstan research reactors (EWG1M in Kurchatov) contains beryllium made core. The results of current examination of that core allow using it without replacement long time yet (at least for next five-ten years). Nevertheless the problem how to utilize such irradiated beryllium becomes actual issue for Kazakhstan even today. Since Kazakhstan is the member of ITER/DEMO Reactors Projects and is permanently considered as possible provider of huge amount of beryllium for those reactors so that is the reason for starting studies of possibilities of large scale processing/recycling of such disposed irradiated beryllium. It is clear that the Ulba Metallurgical Plant is considered as the best site for it in Kazakhstan. The draft plan how to organize experimental studies of irradiated beryllium disposals in Kazakhstan involving National Nuclear Center, National University (Almaty), JSC ''Ulba Metallurgical Plant'' (Ust-Kamenogorsk) would be presented in this paper as well as proposals to arrange international collaboration in that field through ISTC (International Science Technology Center, Moscow). (author)

Effect of transient heating loads on beryllium

International Nuclear Information System (INIS)

Kupriyanov, Igor B.; Porezanov, Nicolay P.; Nikolaev, Georgyi N.; Kurbatova, Liudmila A.; Podkovyrov, Vyacheslav L.; Muzichenko, Anatoliy D.; Zhitlukhin, Anatoliy M.; Khimchenko, Leonid N.; Gervash, Alexander A.

2014-01-01

Highlights: • We study the effect of transient plasma loads on beryllium erosion and surface microstructure. • Beryllium targets were irradiated by plasma streams with energy of 0.5–1 MJ/m 2 at ∼250 °C. • Under plasma loads 0.5–1 MJ/m 2 cracking of beryllium surface is rather slight. • Under 0.5 MJ/m 2 the mass loss of Be is no more than 0.2 g/m 2 shot and decreasing with shots number. • Under 1 MJ/m 2 maximum mass loss of beryllium was 3.7 g/m 2 shot and decreasing with shots number. - Abstract: Beryllium will be used as a plasma facing material for ITER first wall. It is expected that erosion of beryllium under transient plasma loads such as the edge-localized modes (ELMs) and disruptions will mainly determine a lifetime of ITER first wall. The results of recent experiments with the Russian beryllium of TGP-56FW ITER grade on QSPA-Be plasma gun facility are presented. The Be/CuCrZr mock-ups were exposed to upto 100 shots by deuterium plasma streams with pulse duration of 0.5 ms at ∼250 °C and average heat loads of 0.5 and 1 MJ/m 2 . Experiments were performed at 250 °C. The evolution of surface microstructure and cracks morphology as well as beryllium mass loss are investigated under erosion process

The Cryogenic Properties of Several Aluminum-Beryllium Alloys and a Beryllium Oxide Material

Science.gov (United States)

Gamwell, Wayne R.; McGill, Preston B.

2003-01-01

Performance related mechanical properties for two aluminum-beryllium (Al-Be) alloys and one beryllium-oxide (BeO) material were developed at cryogenic temperatures. Basic mechanical properties (Le., ultimate tensile strength, yield strength, percent elongation, and elastic modulus were obtained for the aluminum-beryllium alloy, AlBeMetl62 at cryogenic [-195.5"C (-320 F) and -252.8"C (-423"F)I temperatures. Basic mechanical properties for the Be0 material were obtained at cyrogenic [- 252.8"C (-423"F)] temperatures. Fracture properties were obtained for the investment cast alloy Beralcast 363 at cryogenic [-252.8"C (-423"F)] temperatures. The AlBeMetl62 material was extruded, the Be0 material was hot isostatic pressing (HIP) consolidated, and the Beralcast 363 material was investment cast.

The beryllium production at Ulba metallurgical plant (Ust-Kamenogrsk, Kazakhstan)

Energy Technology Data Exchange (ETDEWEB)

Dvinskykh, E.M.; Savchuk, V.V.; Tuzov, Y.V. [Ulba Metallurgical Plant (Zavod), Ust-Kamenogorsk, Abay prospect 102 (Kazakhstan)

1998-01-01

The Report includes data on beryllium production of Ulba metallurgical plant, located in Ust-Kamenogorsk (Kazakhstan). Beryllium production is showed to have extended technological opportunities in manufacturing semi-products (beryllium ingots, master alloys, metallic beryllium powders, beryllium oxide) and in production of structural beryllium and its parts. Ulba metallurgical plant owns a unique technology of beryllium vacuum distillation, which allows to produce reactor grades of beryllium with a low content of metallic impurities. At present Ulba plant does not depend on raw materials suppliers. The quantity of stored raw materials and semi-products will allow to provide a 25-years work of beryllium production at a full capacity. The plant has a satisfactory experience in solving ecological problems, which could be useful in ITER program. (author)

Beryllium poisonings; Les intoxications par le beryllium

Energy Technology Data Exchange (ETDEWEB)

Alibert, S.

1959-03-15

This note reports a bibliographical study of beryllium toxicity. Thus, this bibliographical review addresses and outlines aspects and issues like aetiology, cases of acute poisoning (cutaneous manifestations, pulmonary manifestations), chronic poisoning (cutaneous, pulmonary and bone manifestations), excretion and localisation, and prognosis.

The immunotoxicity of beryllium

International Nuclear Information System (INIS)

Reeves, A.L.

1983-01-01

In the disease berylliosis, granulomatous hypersensitivity is the specific immune response to tissue contact with a poorly soluble particle of beryllium compound, mediated through the accumulation and proliferation of reticuloendothelial cells. A review is given of the work accomplished since the 1950's and particularly since the 1970's to elucidate the nature and consequences of this response to beryllium and its compounds. (U.K.)

Investigation of beryllium/steam interaction

Energy Technology Data Exchange (ETDEWEB)

Chekhonadskikh, A.M.; Vurim, A.D.; Vasilyev, Yu.S.; Pivovarov, O.S. [Inst. of Atomic Energy National Nuclear Center of the Republic of Kazakstan Semipalatinsk (Kazakhstan); Shestakov, V.P.; Tazhibayeva, I.L.

1998-01-01

In this report program on investigations of beryllium emissivity and transient processes on overheated beryllium surface attacked by water steam to be carried out in IAE NNC RK within Task S81 TT 2096-07-16 FR. The experimental facility design is elaborated in this Report. (author)

Assessment of LANL beryllium waste management documentation

International Nuclear Information System (INIS)

Danna, J.G.; Jennrich, E.A.; Lund, D.M.; Davis, K.D.; Hoevemeyer, S.S.

1991-04-01

The objective of this report is to determine present status of the preparation and implementation of the various high priority documents required to properly manage the beryllium waste generated at the Laboratory. The documents being assessed are: Waste Acceptance Criteria, Waste Characterization Plan, Waste Certification Plan, Waste Acceptance Procedures, Waste Characterization Procedures, Waste Certification Procedures, Waste Training Procedures and Waste Recordkeeping Procedures. Beryllium is regulated (as a dust) under 40 CFR 261.33 as ''Discarded commercial chemical products, off specification species, container residues and spill residues thereof.'' Beryllium is also identified in the 3rd thirds ruling of June 1, 1990 as being restricted from land disposal (as a dust). The beryllium waste generated at the Laboratory is handled separately because beryllium has been identified as a highly toxic carcinogenic material

Radium in baggerspecie afkomstig uit het Rijnmondgebied

NARCIS (Netherlands)

Bijwaard H; Overwater RMW; Glastra P; Nissan LA; LSO

2003-01-01

The radium concentration was measured in 25 samples of harbour sludge taken from the Rijnmond area (Rotterdam harbours and the Nieuwe Waterweg) in 2002. High radium levels were found near the former discharge points of the phosphate ore processing plants, confirming the results of previous

Chronic Beryllium Disease Prevention Program Report

Energy Technology Data Exchange (ETDEWEB)

Lee, S

2012-03-29

This document describes how Lawrence Livermore National Laboratory (LLNL) meets the requirements and management practices of federal regulation 10 CFR 850, 'Chronic Beryllium Disease Prevention Program (CBDPP).' This revision of the LLNL CBDPP incorporates clarification and editorial changes based on lessons learned from employee discussions, observations and reviews of Department of Energy (DOE) Complex and commercial industry beryllium (Be) safety programs. The information is used to strengthen beryllium safety practices at LLNL, particularly in the areas of: (1) Management of small parts and components; and (2) Communication of program status to employees. Future changes to LLNL beryllium activities and on-going operating experience will be incorporated into the program as described in Section S, 'Performance Feedback.'

Conditioning technology of spent radium sources

International Nuclear Information System (INIS)

Kang, Il Sik; Kim, K. J.; Jang, K. D.

2001-03-01

In order to avoid accidents that could be resulted from improper storage of spent radium sources, it is necessary to condition and store them safely. The program for safe conditioning of spent radium sources by IAEA has been established to assist the developing countries. The main object of this report is to understand well and apply the technology that was applied in conditioning the national inventory of Ra-226 sources in Myanmar, as a part of IAEA's project by the Korean expert team. The report is the result that the Korean expert team carried out in Myanmar under the project title 'Radium Conditioning Service in Myanmar(INT4131-06646C)'. As a result of the mission, a whole inventory, 1,429.5 mCi of spent radium sources was safely conditioned by the Korean expert team according to the manual under the supervision of IAEA's technical officer, Mr. Al-Mughrabi, and under the control of DAE authority. These sources were encapsuled in 27 small capsules and 3 large capsules, and conditioned in 3 lead shields, producing 3 packages. The inventories were distributed into 3 shielding devices, holding 500, 459.5, and 470 mCi

Radium-226 in wetland birds from Florida phosphate mines

International Nuclear Information System (INIS)

Myers, O.B.; Marion, W.R.; O'Meara, T.E.; Roessler, C.E.

1989-01-01

Radium-226 is a naturally-occurring radionuclide found in enhanced levels at Florida phosphate mines. We inventoried levels of radium-226 in the tissues of 4 wetland bird species from 2 mined and 2 umined areas in Florida. Bone tissues of wood duck (Aix sponsa), mottled duck (Anas fulvigula), common moorhen (Gallinula chloropus), and double-crested cormorant (Phalacrocorax auritus) colleted at phosphate mines contained more radium-226 than tissues from unmined areas. Radium-226 concentrations in these birds were within guidelines inferred from radiological standards designed for human protection and should not adversely affect bird populations

Beryllium concentration in pharyngeal tonsils in children

Directory of Open Access Journals (Sweden)

Ewa Nogaj

2014-06-01

Full Text Available Power plant dust is believed to be the main source of the increased presence of the element beryllium in the environment which has been detected in the atmospheric air, surface waters, groundwater, soil, food, and cigarette smoke. In humans, beryllium absorption occurs mainly via the respiratory system. The pharyngeal tonsils are located on the roof of the nasopharynx and are in direct contact with dust particles in inhaled air. As a result, the concentration levels of beryllium in the pharyngeal tonsils are likely to be a good indicator of concentration levels in the air. The presented study had two primary aims: to investigate the beryllium concentration in pharyngeal tonsils in children living in southern Poland, and the appropriate reference range for this element in children’s pharyngeal tonsils. Pharyngeal tonsils were extracted from a total of 379 children (age 2–17 years, mean 6.2 ± 2.7 years living in southern Poland. Tonsil samples were mineralized in a closed cycle in a pressure mineralizer PDS 6, using 65% spectrally pure nitric acid. Beryllium concentration was determined using the ICP-AES method with a Perkin Elmer Optima 5300DVTM. The software Statistica v. 9 was used for the statistical analysis. It was found that girls had a significantly greater beryllium concentration in their pharyngeal tonsils than boys. Beryllium concentration varies greatly, mostly according to the place of residence. Based on the study results, the reference value for beryllium in pharyngeal tonsils of children is recommended to be determined at 0.02–0.04 µg/g.

Barium and radium migration in unconsolidated Canadian geological materials

International Nuclear Information System (INIS)

Gillham, R.W.; Sharma, H.D.; Reddy, M.R.; Cooper, E.L.; Cherry, J.A.

1981-05-01

This report describes the results of laboratory studies on the distribution coefficients of radium and barium in samples of unconsolidated geologic materials. Graphs of Ksub(d) versus solution concentration for the respective elements showed constant Ksub(d) values in the low concentration range suggesting that, at low concentrations, a distribution coefficient is a valid means of representing the geochemical reactions of both barium and radium. The Ksub(d) values for barium range between 60 and 3500 ml/g. The values appear to be influenced by the amount of barium occurring naturally in the soil materials and thus there is little possiblility of using barium as an analog of radium in laboratory experiments. The Ksub(d) values of radium vary from 50 to 1000 ml/g indicating that a wide range of geological materials have a substantial capacity to retard the migration of radium

New audio applications of beryllium metal

International Nuclear Information System (INIS)

Sato, M.

1977-01-01

The major applications of beryllium metal in the field of audio appliances are for the vibrating cones for the two types of speakers 'TWITTER' for high range sound and 'SQUAWKER' for mid range sound, and also for beryllium cantilever tube assembled in stereo cartridge. These new applications are based on the characteristic property of beryllium having high ratio of modulus of elasticity to specific gravity. The production of these audio parts is described, and the audio response is shown. (author)

Status of beryllium study for fusion in RF

International Nuclear Information System (INIS)

Khomutov, A.M.; Kupriyanov, I.B.; Markushkin, Yu.E.; Gervash, A.; Kolbasov, B.N.

2004-01-01

The main directions of research activities in the field of beryllium application science and technology carried out in Russia during 2001-2003 have been reviewed. The main results of these investigations have been highlighted. First wall and port-limier. The investigation on the actively cooled components with beryllium cladding is under progress objecting on the clarification of their ultimate thermo cycling capabilities. The study of behavior of bulk beryllium and the boundary region of the contact with the cooling structure under the intensive thermo cycling loading and neutron irradiation have been the object of consideration in particular. The works on the optimization and modification of industrial fabrication processes for commercial scaled production of beryllium tile were also under way. The influence of neutron irradiation. The new experimental data on the nuclear properties of several Russian beryllium grades has been obtained. The samples have been subjected to the high neutron dozes. The influence of low temperature (70-200degree C) neutron irradiation on the thermal conductivity has been examined in particular. The interrelations of the helium inventory and temperature of neutron irradiation with tritium release out of irradiated beryllium samples have been analyzed. The beryllium associated safety questions. The experiments on the modeling of normal working conditions and conditions imitating the plasma disruption events in ITER performance scenario have been continued. The new experimental information on the coefficient of pulverization of beryllium and the accumulation of deuterium in beryllium under the action of proton beam has been collected. The dependence of the reaction rate constant for the beryllium oxidation by the water vapor for different conditions has been analyzed. The compact, porous and powder beryllium samples have been tested at the wide range of temperature, pressure and duration of reaction with water vapor. The calculating

Research of flaw assessment methods for beryllium reflector elements

International Nuclear Information System (INIS)

Shibata, Akira; Ito, Masayasu; Takemoto, Noriyuki; Tanimoto, Masataka; Tsuchiya, Kunihiko; Nakatsuka, Masafumi; Ohara, Hiroshi; Kodama, Mitsuhiro

2012-02-01

Reflector elements made from metal beryllium is widely used as neutron reflectors to increase neutron flux in test reactors. When beryllium reflector elements are irradiated by neutron, bending of reflector elements caused by swelling occurs, and beryllium reflector elements must be replaced in several years. In this report, literature search and investigation for non-destructive inspection of Beryllium and experiments for Preliminary inspection to establish post irradiation examination method for research of characteristics of metal beryllium under neutron irradiation were reported. (author)

Electrodeposition of Radium

International Nuclear Information System (INIS)

Crespo, M.T.; Jimenez, A.S.

1996-01-01

A study of different electrodeposition methods of radium for its measurement by alpha-spectrometry is presented. The recommended procedure uses an aqueous solution of ammonium oxalate and nitric acid in the presence of microgram amounts of platinum as electrolyte

Process for the removal of radium from acidic solutions containing same

Science.gov (United States)

Scheitlin, F.M.

The invention is a process for the removal of radium from acidic aqueous solutions. In one aspect, the invention is a process for removing radium from an inorganic-acid solution. The process comprises contacting the solution with coal fly ash to effect adsorption of the radium on the ash. The radium-containing ash then is separated from the solution. The process is simple, comparatively inexpensive, and efficient. High radium-distribution coefficients are obtained even at room temperature. Coal fly ash is an inexpensive, acid-resistant, high-surface-area material which is available in large quantities throughout the United States. The invention is applicable, for example, to the recovery of /sup 226/Ra from nitric acid solutions which have been used to leach radium from uranium-mill tailings.

Accumulation of radium in relation to some chemical analogues in Dicranopteris linearis

International Nuclear Information System (INIS)

Chao, J.H.; Chuang, C.Y.

2011-01-01

This study elucidates the uptake and accumulation of radium in the field-growing fern Dicranopteris linearis by relating the radium concentration to some potential chemical analogues, including alkaline earth metals, rare earth elements, and some important heavy metals. Time-dependent accumulation of radium and these chemical analogues for D. linearis were described by the 228 Th/ 228 Ra activity ratio, an index for inferring plant age. The correlation between radium and these elements was assessed by statistical analysis and used as a reference to elucidate the uptake and accumulation of radium in relation to the chemical analogues. Analytical and statistical results showed that the concentrations of alkaline earth metals (except for Mg) rare earth elements and some heavy metals in D. linearis increased linearly with plant age. These elements, exhibiting a similar accumulation pattern to radium and significant correlation coefficients with radium, were considered as the chemical analogues to radium. Additionally, the plant/soil concentration ratios (CRs) for radium and most of these analogues in D. linearis exceeded 1, consistent with the definition of hyper-accumulator plants.

Alteration of the retinoblastoma gene locus in radium-exposed individuals

International Nuclear Information System (INIS)

Hardwick, J.P.; Schlenker, R.; Huberman, E.

1991-01-01

This study was performed to determine if the retinoblastoma suppressor gene was altered in individuals exposed to radium. We analyzed the Rb gene in 30 individuals, 17 of whom were exposed to radium either occupationally or iatrogenically. In the kidney DNA from four of nine radium-exposed individuals, the Rb gene was deleted. Three of these alterations in the Rb gene were internal deletions, which resulted in the absence of Rb mRNA accumulation. These results imply that the Rb gene is susceptible to radium-induced damage and confirm previous showing that radiation preferentially causes genomic deletions. The pronounced alterations in the non-tumorigenic femurs from radium-exposed individuals suggests that in the many years of exposure there was a selection of cells with alterations, presumably because of their growth advantage. Also it implies that deletions of one of the Rb alleles can be one of the events (perhaps an initial one) in the progression of radium-induced sarcomas. 11 refs., 2 figs

Beryllium R and D for fusion applications

International Nuclear Information System (INIS)

Scaffidi-Argentina, F.; Longhurst, G.R.; Shestakov, V.; Kawamura, H.

2000-01-01

Beryllium is one of the primary candidates as both plasma-facing material (PFM) and neutron multiplier in the next-step fusion reactors. Both sintered-product blocks and pebbles are considered in fusion reactor designs. Beryllium evaporated on carbon tiles has also been used in Joint European Torus (JET) and may be considered for other designs. Future efforts are directed toward the pebble form of beryllium. Research and evaluations of data are underway to determine the most attractive material processing approaches in terms of fabrication cost and quality; technical issues associated with heat transfer; thermal, mechanical and irradiation stability; safety and tritium release. Beryllium plasma-facing components will require periodic repair or replacement, therefore disposal or recycling of activated and tritiated beryllium will also be a concern. Beryllium as a component of the molten salt, Flibe is also being considered in novel approaches to the plasma-structure interface. This paper deals with the main issues related to the use of Be in a fusion reactor as both neutron multiplier and first wall material. These issues include potential reactions with steam during accidents and the health and environmental aspects of its use, reprocessing and reuse, or disposal

Beryllium R and D for fusion applications

Energy Technology Data Exchange (ETDEWEB)

Scaffidi-Argentina, F. E-mail: francesco.scaffidi@iket.fzk.de; Longhurst, G.R.; Shestakov, V.; Kawamura, H

2000-11-01

Beryllium is one of the primary candidates as both plasma-facing material (PFM) and neutron multiplier in the next-step fusion reactors. Both sintered-product blocks and pebbles are considered in fusion reactor designs. Beryllium evaporated on carbon tiles has also been used in Joint European Torus (JET) and may be considered for other designs. Future efforts are directed toward the pebble form of beryllium. Research and evaluations of data are underway to determine the most attractive material processing approaches in terms of fabrication cost and quality; technical issues associated with heat transfer; thermal, mechanical and irradiation stability; safety and tritium release. Beryllium plasma-facing components will require periodic repair or replacement, therefore disposal or recycling of activated and tritiated beryllium will also be a concern. Beryllium as a component of the molten salt, Flibe is also being considered in novel approaches to the plasma-structure interface. This paper deals with the main issues related to the use of Be in a fusion reactor as both neutron multiplier and first wall material. These issues include potential reactions with steam during accidents and the health and environmental aspects of its use, reprocessing and reuse, or disposal.

Beryllium-copper reactivity in an ITER joining environment

International Nuclear Information System (INIS)

Odegard, B.C.; Cadden, C.H.; Yang, N.Y.C.

1998-01-01

Beryllium-copper reactivity was studied using test parameters being considered for use in the ITER reactor. In this application, beryllium-copper tiles are produced using a low-temperature copper-copper diffusion bonding technique. Beryllium is joined to copper by first plating the beryllium with copper followed by diffusion bonding the electrodeposited (ED) copper to a wrought copper alloy (CuNiBe) at 450 C, 1-3 h using a hot isostatic press (HIP). In this bonded assembly, beryllium is the armor material and the CuNiBe alloy is the heat sink material. Interface temperatures in service are not expected to exceed 350 C. For this study, an ED copper-beryllium interface was subjected to diffusion bonding temperatures and times to study the reaction products. Beryllium-copper assemblies were subjected to 350, 450 and 550 C for times up to 200 h. Both BeCu and Be 2 Cu intermetallic phases were detected using scanning electron microscopy and quantitative microprobe analysis. Growth rates were determined experimentally for each phase and activation energies for formation were calculated. The activation energies were 66 mol and 62 kJ mol -1 for the BeCu and Be 2 Cu, respectively. Tensile bars were produced from assemblies consisting of coated beryllium (both sides) sandwiched between two blocks of Hycon-3. Tensile tests were conducted to evaluate the influence of these intermetallics on the bond strength. Failure occurred at the beryllium-copper interface at fracture strengths greater than 300 MPa for the room-temperature tests. (orig.)

BERYLLIUM MEASUREMENT IN COMMERCIALLY AVAILABLE WET WIPES

Energy Technology Data Exchange (ETDEWEB)

Youmans-Mcdonald, L.

2011-02-18

Analysis for beryllium by fluorescence is now an established method which is used in many government-run laboratories and commercial facilities. This study investigates the use of this technique using commercially available wet wipes. The fluorescence method is widely documented and has been approved as a standard test method by ASTM International and the National Institute for Occupational Safety and Health (NIOSH). The procedure involves dissolution of samples in aqueous ammonium bifluoride solution and then adding a small aliquot to a basic hydroxybenzoquinoline sulfonate fluorescent dye (Berylliant{trademark} Inc. Detection Solution Part No. CH-2) , and measuring the fluorescence. This method is specific to beryllium. This work explores the use of three different commercial wipes spiked with beryllium, as beryllium acetate or as beryllium oxide and subsequent analysis by optical fluorescence. The effect of possible interfering metals such as Fe, Ti and Pu in the wipe medium is also examined.

Beryllium Measurement In Commercially Available Wet Wipes

International Nuclear Information System (INIS)

Youmans-Mcdonald, L.

2011-01-01

Analysis for beryllium by fluorescence is now an established method which is used in many government-run laboratories and commercial facilities. This study investigates the use of this technique using commercially available wet wipes. The fluorescence method is widely documented and has been approved as a standard test method by ASTM International and the National Institute for Occupational Safety and Health (NIOSH). The procedure involves dissolution of samples in aqueous ammonium bifluoride solution and then adding a small aliquot to a basic hydroxybenzoquinoline sulfonate fluorescent dye (Berylliant(trademark) Inc. Detection Solution Part No. CH-2) , and measuring the fluorescence. This method is specific to beryllium. This work explores the use of three different commercial wipes spiked with beryllium, as beryllium acetate or as beryllium oxide and subsequent analysis by optical fluorescence. The effect of possible interfering metals such as Fe, Ti and Pu in the wipe medium is also examined.

Beryllium dust generation resulting from plasma bombardment

International Nuclear Information System (INIS)

Doerner, R.; Mays, C.

1997-01-01

The beryllium dust resulting from erosion of beryllium samples subjected to plasma bombardment has been measured in PISCES-B. Loose surface dust was found to be uniformly distributed throughout the device and accounts for 3% of the eroded material. A size distribution measurement of the loose surface dust shows an increasing number of particles with decreasing diameter. Beryllium coatings on surfaces with a line of sight view of the target interaction region account for an additional 33% of the eroded beryllium material. Flaking of these surface layers is observed and is thought to play a significant role in dust generation inside the vacuum vessel. (orig.)

Investigations of the ternary system beryllium-carbon-tungsten and analyses of beryllium on carbon surfaces

International Nuclear Information System (INIS)

Kost, Florian

2009-01-01

Beryllium, carbon and tungsten are planned to be used as first wall materials in the future fusion reactor ITER. The aim of this work is a characterization of mixed material formation induced by thermal load. To this end, model systems (layers) were prepared and investigated, which give insight into the basic physical and chemical concepts. Before investigating ternary systems, the first step was to analyze the binary systems Be/C and Be/W (bottom-up approach), where the differences between the substrates PG (pyrolytic graphite) and HOPG (highly oriented pyrolytic graphite) were of special interest. Particularly X-ray photoelectron spectroscopy (XPS), low energy ion scattering (ISS) and Rutherford backscattering spectroscopy (RBS) were used as analysis methods. Beryllium evaporated on carbon shows an island growth mode, whereas a closed layer can be assumed for layer thicknesses above 0.7 nm. Annealing of the Be/C system induces Be 2 C island formation for T≥770 K. At high temperatures (T≥1170 K), beryllium carbide dissociates, resulting in (metallic) beryllium desorption. For HOPG, carbide formation starts at higher temperatures compared to PG. Activation energies for the diffusion processes were determined by analyzing the decreasing beryllium amount versus annealing time. Surface morphologies were characterized using angle-resolved XPS (ARXPS) and atomic force microscopy (AFM). Experiments were performed to study processes in the Be/W system in the temperature range from 570 to 1270 K. Be 2 W formation starts at 670 K, a complete loss of Be 2 W is observed at 1170 K due to dissociation (and subsequent beryllium desorption). Regarding ternary systems, particularly Be/C/W and C/Be/W were investigated, attaching importance to layer thickness (reservoir) variations. At room temperature, Be 2 C, W 2 C, WC and Be 2 W formation at the respective interfaces was observed. Further Be 2 C is forming with increasing annealing temperatures. Depending on the layer

Technical issues for beryllium use in fusion blanket applications

International Nuclear Information System (INIS)

McCarville, T.J.; Berwald, D.H.; Wolfer, W.; Fulton, F.J.; Lee, J.D.; Maninger, R.C.; Moir, R.W.; Beeston, J.M.; Miller, L.G.

1985-01-01

Beryllium is an excellent non-fissioning neutron multiplier for fusion breeder and fusion electric blanket applications. This report is a compilation of information related to the use of beryllium with primary emphasis on the fusion breeder application. Beryllium resources, production, fabrication, properties, radiation damage and activation are discussed. A new theoretical model for beryllium swelling is presented

Production of beryllium oxide of nuclear purity from beryl

Energy Technology Data Exchange (ETDEWEB)

Copat, A; Sood, S P

1984-01-01

Production of beryllium oxide from beryl by the fluoride process was optimized in this study. Optimum results were obtained using a mixture of sodium hexafluorsilicate and sodium hexafluorferrate as flux and calcinating at 740/sup 0/C for 2 hours. The beryllium concentrate produced was further purified by crystallization as beryllium sulfate to obtain nuclear grade beryllium oxide

Production of beryllium oxide of nuclear purity from beryl

International Nuclear Information System (INIS)

Copat, A.; Sood, S.P.

1983-01-01

Production of beryllium oxide from beryl by the fluoride process was optimized in this study. Optimum results were obtained using a mixture of sodium hexafluorsilicate and sodium hexafluorferrate as flux and calcinating at 740 0 C for 2 hours. The beryllium concentrate produced was further purified by crystallization as beryllium sulfate to obtain nuclear grade beryllium oxide (Author) [pt

Practical recommendations for radium-223 treatment of metastatic castration-resistant prostate cancer

International Nuclear Information System (INIS)

Du, Yong; Carrio, Ignasi; De Vincentis, Giuseppe; Fanti, Stefano; Ilhan, Harun; Mommsen, Caroline; Nitzsche, Egbert; Sundram, Francis; Vogel, Wouter; Oyen, Wim; Lewington, Val

2017-01-01

Radium Ra 223 dichloride (radium-223, Xofigo registered) is the first targeted alpha therapy for patients with castration-resistant prostate cancer and symptomatic bone metastases. Radium-223 provides a new treatment option for this setting, but also necessitates a new treatment management approach. We provide straightforward and practical recommendations for European nuclear medicine centres to optimize radium-223 service provision. An independent research consultancy agency observed radium-223 procedures and conducted interviews with all key staff members involved in radium-223 treatment delivery in 11 nuclear medicine centres across six countries (Germany, Italy, the Netherlands, Spain, Switzerland and the UK) experienced in administering radium-223. The findings were collated and discussed at a meeting of experts from these centres, during which key consensus recommendations were defined. The recommendations cover centre organization and preparation; patient referral; radium-223 ordering, preparation and disposal; radium-223 treatment delivery/administration; and patient experience. Guidance includes structured coordination and communication within centres and multidisciplinary teams, focusing on sharing best practice to provide high-quality, patient-centred care throughout the treatment pathway. These expert recommendations are intended to complement existing management guidelines. Sharing best practice and experience will help nuclear medicine centres to optimize radium-223 service provision and improve patient care. (orig.)

Practical recommendations for radium-223 treatment of metastatic castration-resistant prostate cancer

Energy Technology Data Exchange (ETDEWEB)

Du, Yong [The Royal Marsden NHS Foundation Trust, Department of Nuclear Medicine and PET/CT, London (United Kingdom); Carrio, Ignasi [Hospital Sant Pau, Barcelona (Spain); De Vincentis, Giuseppe [Policlinico Umberto I University Hospital Rome, Rome (Italy); Fanti, Stefano [University Hospital Bologna, Bologna (Italy); Ilhan, Harun [Ludwig-Maximilians-University Hospital, Munich (Germany); Mommsen, Caroline [Praxis fuer diagnostische und therapeutische Nuklearmedizin Berlin, Berlin (Germany); Nitzsche, Egbert [Canton Hospital Aarau, Aarau (Switzerland); Sundram, Francis [University Hospital Southampton NHS Foundation Trust, Southampton (United Kingdom); Vogel, Wouter [The Netherlands Cancer Institute, Amsterdam (Netherlands); Oyen, Wim [The Royal Marsden NHS Foundation Trust, Department of Nuclear Medicine and PET/CT, London (United Kingdom); The Institute of Cancer Research, London (United Kingdom); Lewington, Val [Guy' s and St Thomas' NHS Foundation Trust, London (United Kingdom)

2017-09-15

Radium Ra 223 dichloride (radium-223, Xofigo registered) is the first targeted alpha therapy for patients with castration-resistant prostate cancer and symptomatic bone metastases. Radium-223 provides a new treatment option for this setting, but also necessitates a new treatment management approach. We provide straightforward and practical recommendations for European nuclear medicine centres to optimize radium-223 service provision. An independent research consultancy agency observed radium-223 procedures and conducted interviews with all key staff members involved in radium-223 treatment delivery in 11 nuclear medicine centres across six countries (Germany, Italy, the Netherlands, Spain, Switzerland and the UK) experienced in administering radium-223. The findings were collated and discussed at a meeting of experts from these centres, during which key consensus recommendations were defined. The recommendations cover centre organization and preparation; patient referral; radium-223 ordering, preparation and disposal; radium-223 treatment delivery/administration; and patient experience. Guidance includes structured coordination and communication within centres and multidisciplinary teams, focusing on sharing best practice to provide high-quality, patient-centred care throughout the treatment pathway. These expert recommendations are intended to complement existing management guidelines. Sharing best practice and experience will help nuclear medicine centres to optimize radium-223 service provision and improve patient care. (orig.)

Mechanical performance of irradiated beryllium pebbles

Energy Technology Data Exchange (ETDEWEB)

Scaffidi-Argentina, F.; Dalle-Donne, M.; Werle, H. [Forschungszentrum Karlsruhe GmbH Technik und Umwelt (Germany). Inst. fuer Neutronenphysik und Reaktortechnik

1998-01-01

For the Helium Cooled Pebble Bed (HCPB) Blanket, which is one of the two reference concepts studied within the European Fusion Technology Programme, the neutron multiplier consists of a mixed bed of about 2 and 0.1-0.2 mm diameter beryllium pebbles. Beryllium has no structural function in the blanket, however microstructural and mechanical properties are important, as they might influence the material behavior under neutron irradiation. The EXOTIC-7 as well as the `Beryllium` experiments carried out in the HFR reactor in Petten are considered as the most detailed and significant tests for investigating it. This paper reviews the present status of beryllium post-irradiation examinations performed at the Forschungszentrum Karlsruhe with samples from these irradiation experiments, emphasizing the effects of irradiation of essential material properties and trying to elucidate the processes controlling the property changes. The microstructure, the porosity distribution, the impurity content, the behavior under compression loads and the compatibility of the beryllium pebbles with lithium orthosilicate (Li{sub 4}SiO{sub 4}) during the in-pile irradiation are presented and critically discussed. Qualitative information on ductility and creep obtained by hardness-type measurements are also supplied. (author)

Removal of radium-226 from uranium mining effluents

International Nuclear Information System (INIS)

Averill, D.W.; Moffett, D.; Webber, R.T.; Whittle, L.; Wood, J.A.

1984-12-01

Uranium mining and milling operations usually generate large quantities of solid and liquid waste materials. A slurry, consisting of waste rock and chemical solutions from the milling operation, is discharged to impoundment areas (tailings basins). Most of the radioactive material dissolved in tailings slurries is precipitated by the addition of lime and limestone prior to discharge from the mill. However, the activity of one radioisotope, radium-226, remains relatively high in the tailings basin effluents. In Canada, radium-226 is removed from uranium mining and milling effluents by the addition of barium chloride to precipitate barium-radium sulphate [(Ba,Ra)SO 4 ]. Although dissolved radium-226 activities are generally reduced effectively, the process is considered to have two undesirable characteristics: the first related to suspended radium-226 in the effluents and the second to ultimate disposal of the (Ba,Ra)SO 4 sludge. A government-industry mining task force established a radioactivity sub-group in 1974 to assist in the development of effluent guidelines and regulations for the uranium mining industry (Radioactivity Sub-group, 1974). The investigation of more effective removal methods was recommended, including the development of mechanical treatment systems as alternatives to settling ponds. Environment Canada's Wastewater Technology Centre (WTC) initiated a bench scale study in March, 1976 which was designed to assess the feasibility of using precipitation, coagulation, flocculation and sedimentation for the removal of radium-226. In 1977, the study was accelerated with financial assistance from the Atomic Energy Control Board. The results were favourable, with improved radium removals obtained in bench scale batch tests using barium chloride as the precipitant and either alum or ferric chloride as the coagulant. A more comprehensive bench scale and pilot scale process development and demonstration program was formulated. The results of the joint study

Preliminary results for explosion bonding of beryllium to copper

International Nuclear Information System (INIS)

Butler, D.J.; Dombrowski, D.E.

1995-01-01

This program was undertaken to determine if explosive bonding is a viable technique for joining beryllium to copper substrates. The effort was a cursory attempt at trying to solve some of the problems associated with explosive bonding beryllium and should not be considered a comprehensive research effort. There are two issues that this program addressed. Can beryllium be explosive bonded to copper substrates and can the bonding take place without shattering the beryllium? Thirteen different explosive bonding iterations were completed using various thicknesses of beryllium that were manufactured with three different techniques

The environmental behaviour of radium. V.1

International Nuclear Information System (INIS)

1990-01-01

The objective of this publication is to provide an up to date review of the environmental behaviour of radium, including methods for analysis, assessment and control. The need for a reference text on the subject was identified at an early stage of the International Atomic Energy Agency's Co-ordinated Research Programme (CRP) on radium behaviour in relation to uranium mining and milling wastes, which began in 1976. There were two CRPs: (1) The Source, Distribution, Movement and Deposition of Radium in Inland Waterways and Aquifers (1976-1980; final report: IAEA-TECDOC-301, published in 1984). (2) The Environmental Migration of Radium and Other Contaminants Present in Liquid and Solid Wastes from the Mining and Milling of Uranium (1981-1985; final report: IAEA-TECDOC-370, published in 1986). This publication deals with the sources, properties, environmental behaviour and the methods of analysis, control and assessment of 226 Ra. It is an outgrowth of Agency programmes directed towards the environmental problems involved in uranium mining and milling. The emphasis in several of the sections reflects these origins. For example, many of the contributions in Volume 2 of this report on technologically enhanced sources of radium (Part 1), methods of control and abatement (Part 2) and the impact on man (Part 3) are concerned with uranium mining and milling. In Volume 1, coverage of the natural distribution (Part 2), analytical methods (Part 3), environmental migration (Part 4) and biological uptake (Part 5), is more general. It is likely that the reader will find the information needed on the environmental behaviour of radium in this report, or will at least find references to other, more appropriate, texts contained in it. Refs, figs and tabs

Preliminary proposal for a beryllium technology program for fusion applications

International Nuclear Information System (INIS)

1985-02-01

The program was designed to provide the answers to the critical issues of beryllium technology needed in fusion blanket designs. The four tasks are as follows: (1) Beryllium property measurements needed for fusion data base. (2) Beryllium stress relaxation and creep measurements for lifetime modelling calculations. (3) Simplified recycle technique development for irradiated beryllium. (4) Beryllium neutron multiplier measurements using manganese bath absolute calibration techniques

The status of beryllium technology for fusion

Energy Technology Data Exchange (ETDEWEB)

Scaffidi-Argentina, F.; Longhurst, G.R. E-mail: gx1@inel.gov; Shestakov, V.; Kawamura, H

2000-12-01

Beryllium was used for a number of years in the Joint European Torus (JET), and it is planned to be used extensively on the lower heat-flux surfaces of the reduced technical objective/reduced cost international thermonuclear experimental reactor (RTO/RC ITER). It has been included in various forms in a number of tritium breeding blanket designs. There are technical advantages but also a number of safety issues associated with the use of beryllium. Research in a variety of technical areas in recent years has revealed interesting issues concerning the use of beryllium in fusion. Progress in this research has been presented at a series of International Workshops on Beryllium Technology for Fusion. The most recent workshop was held in Karlsruhe, Germany on 15-17 September 1999. In this paper, a summary of findings presented there and their implications for the use of beryllium in the development of fusion reactors are presented.

The status of beryllium technology for fusion

International Nuclear Information System (INIS)

Scaffidi-Argentina, F.; Longhurst, G.R.; Shestakov, V.; Kawamura, H.

2000-01-01

Beryllium was used for a number of years in the Joint European Torus (JET), and it is planned to be used extensively on the lower heat-flux surfaces of the reduced technical objective/reduced cost international thermonuclear experimental reactor (RTO/RC ITER). It has been included in various forms in a number of tritium breeding blanket designs. There are technical advantages but also a number of safety issues associated with the use of beryllium. Research in a variety of technical areas in recent years has revealed interesting issues concerning the use of beryllium in fusion. Progress in this research has been presented at a series of International Workshops on Beryllium Technology for Fusion. The most recent workshop was held in Karlsruhe, Germany on 15-17 September 1999. In this paper, a summary of findings presented there and their implications for the use of beryllium in the development of fusion reactors are presented

Ion beam assisted deposition of metal-coatings on beryllium

International Nuclear Information System (INIS)

Tashlykov, I.S.; Tul'ev, V.V.

2015-01-01

Thin films were applied on beryllium substrates on the basis of metals (Cr, Ti, Cu and W) with method of the ion-assisted deposition in vacuum. Me/Be structures were prepared using 20 kV ions irradiation during deposition on beryllium neutral fraction generated from vacuum arc plasma. Rutherford back scattering and computer simulation RUMP code were applied to investigate the composition of the modified beryllium surface. Researches showed that the superficial structure is formed on beryllium by thickness ~ 50-60 nm. The covering composition includes atoms of the deposited metal (0.5-3.3 at. %), atoms of technological impurity carbon (0.8-1.8 at. %) and oxygen (6.3-9.9 at. %), atoms of beryllium from the substrate. Ion assisted deposition of metals on beryllium substrate is accompanied by radiation enhanced diffusion of metals, oxygen atoms in the substrate, out diffusion of beryllium, carbon atoms in the deposited coating and sputtering film-forming ions assists. (authors)

Immobilization of radium in uranium mine and mill tailings

International Nuclear Information System (INIS)

Lutwick, G.D.; Mosher, J.; Tizzard, R.

1982-01-01

Radium has been coprecipitated from solution as the arsenate in which ferric iron, barium, copper and lead are the macro ions. The order of efficiency of the macro ions in removing radium was found to be Ba > Fe > Pb > Cu at a pH of 6. It is expected that at higher pH's i.e., greater than 8, ferric iron will change positions. This change in position will be caused by the formation of ferrate ion hence increasing the solubility of ferric arsenate. The removal of radium from solution by ion exchangers consisting of the arsenates of ferric iron, barium, copper and lead was successful. As the pH is increased from 4 to 10 the efficiency of these exchangers in removing radium increases. The columns removed over 99 percent of the radium at pH's of 5.6 and higher. The order of efficiency of the exchangers in removing radium is not well defined. Thorium has been precipitated as the arsenate over the pH range of 2 to 9.6. This reaction suggests the possibility of using arsenate to remove thorium from uranium mill plant streams and as a reagent to keep thorium in the tailings ponds

Beryllium processing technology review for applications in plasma-facing components

Energy Technology Data Exchange (ETDEWEB)

Castro, R.G.; Jacobson, L.A.; Stanek, P.W.

1993-07-01

Materials research and development activities for the International Thermonuclear Experimental Reactor (ITER), i.e., the next generation fusion reactor, are investigating beryllium as the first-wall containment material for the reactor. Important in the selection of beryllium is the ability to process, fabricate and repair beryllium first-wall components using existing technologies. Two issues that will need to be addressed during the engineering design activity will be the bonding of beryllium tiles in high-heat-flux areas of the reactor, and the in situ repair of damaged beryllium tiles. The following review summarizes the current technology associated with welding and joining of beryllium to itself and other materials, and the state-of-the-art in plasma-spray technology as an in situ repair technique for damaged beryllium tiles. In addition, a review of the current status of beryllium technology in the former Soviet Union is also included.

Beryllium processing technology review for applications in plasma-facing components

International Nuclear Information System (INIS)

Castro, R.G.; Jacobson, L.A.; Stanek, P.W.

1993-07-01

Materials research and development activities for the International Thermonuclear Experimental Reactor (ITER), i.e., the next generation fusion reactor, are investigating beryllium as the first-wall containment material for the reactor. Important in the selection of beryllium is the ability to process, fabricate and repair beryllium first-wall components using existing technologies. Two issues that will need to be addressed during the engineering design activity will be the bonding of beryllium tiles in high-heat-flux areas of the reactor, and the in situ repair of damaged beryllium tiles. The following review summarizes the current technology associated with welding and joining of beryllium to itself and other materials, and the state-of-the-art in plasma-spray technology as an in situ repair technique for damaged beryllium tiles. In addition, a review of the current status of beryllium technology in the former Soviet Union is also included

Beryllium-aluminum alloys for investment castings

International Nuclear Information System (INIS)

Nachtrab, W.T.; Levoy, N.

1997-01-01

Beryllium-aluminum alloys containing greater than 60 wt % beryllium are very favorable materials for applications requiring light weight and high stiffness. However, when produced by traditional powder metallurgical methods, these alloys are expensive and have limited applications. To reduce the cost of making beryllium-aluminum components, Nuclear Metals Inc. (NMI) and Lockheed Martin Electronics and Missiles have recently developed a family of patented beryllium-aluminum alloys that can be investment cast. Designated Beralcast, the alloys can achieve substantial weight savings because of their high specific strength and stiffness. In some cases, weight has been reduced by up to 50% over aluminum investment casting. Beralcast is now being used to make thin wall precision investment castings for several advanced aerospace applications, such as the RAH-66 Comanche helicopter and F-22 jet fighter. This article discusses alloy compositions, properties, casting method, and the effects of cobalt additions on strength

Microstructure Analysis on Beryllium Reflector Blocks of Research Reactors

Energy Technology Data Exchange (ETDEWEB)

Kang, Suk Hoon; Jang, Jin Sung; Jeong, Yong Hwan; Han, Chang Hee; Jung, Yang Il; Kim, Tae Kyu [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Choi, Yong Seok; Oh, Kyu Hwan [Seoul National University, Seoul (Korea, Republic of)

2012-05-15

A pure beryllium has a very low mass absorption coefficient: it has been used as the reflector element material in research reactors. The lifetime of beryllium reflector elements usually determined by the swelling: the swelling leads to dimensional change in the reflector frame, which results in bending or cracking of the parts. The mechanical interference in between parts should be avoided; the anisotropy of beryllium also needs to be considered. A beryllium has hexagonal close-pack (HCP) crystal structure, which is inherently anisotropic. It has virtually no ductility in one direction. There are two main aspects in the manufacturing of beryllium which will affect its isotropy, and those are the powder morphology and the consolidation process. Powder metallurgy permits the material to be produced in isotropic and fine-grained form, which overcomes the crystal structure problem by distributing loads in low ductility oriented grains to high ductility oriented grains. There are three representative consolidating methods to make beryllium reflector blocks. Traditionally, most powder-derived grades of beryllium have been consolidated by vacuum hot-pressing (VHP). A column of loose beryllium powder is compacted under vacuum by the pressure of the opposed upper and lower punches, bringing the billet to final density. The VHP process is directional in nature: it contributes to the anisotropy of the material properties. Another consolidating method for beryllium powder is hot isostatic pressing (HIPing), which will enhance its isotropy. During HIPing, The argon gas exerts pressure uniformly in all directions on the can containing the beryllium powder. The HIP process is effective to improve the isotropy of the resulting material as well as refinement of grain sizes. The last consolidating method is hot extrusion (HE). A roughly close packed beryllium is subjected to severe plastic defomation, the grains are refined and the tensile strength is enhanced. Since the material

Safety handling of beryllium for fusion technology R and D

International Nuclear Information System (INIS)

Yoshida, Hiroshi; Okamoto, Makoto; Terai, Takayuki; Odawara, Osamu; Ashibe, Kusuo; Ohara, Atsushi.

1992-07-01

Feasibility of beryllium use as a blanket neutron multiplier, first wall and plasma facing material has been studied for the D-T burning experiment reactors such as ITER. Various experimental work of beryllium and its compounds will be performed under the conditions of high temperature and high energy particle exposure simulating fusion reactor conditions. Beryllium is known as a hazardous substance and its handling has been carefully controlled by various health and safe guidances and/or regulations in many countries. Japanese regulations for hazardous substance provide various guidelines on beryllium for the protection of industrial workers and environment. This report was prepared for the safe handling of beryllium in a laboratory scale experiments for fusion technology R and D such as blanket development. Major items in this report are; (1) Brief review of guidances and regulations in USA, UK and Japan. (2) Safe handling and administration manuals at beryllium facilities in INEL, LANL and JET. (3) Conceptual design study of beryllium handling facility for small to mid-scale blanket R and D. (4) Data on beryllium toxicity, example of clinical diagnosis of beryllium disease, and environmental occurence of beryllium. (5) Personnel protection tools of Japanese Industrial Standard for hazardous substance. (author) 61 refs

Hydrogen transport behavior of beryllium

Energy Technology Data Exchange (ETDEWEB)

Anderl, R.A.; Hankins, M.R.; Longhurst, G.R.; Pawelko, R.J. (Idaho National Engineering Lab., EG and G Idaho, Inc., Idaho Falls, ID (United States)); Macaulay-Newcombe, R.G. (Dept. of Engineering Physics, Univ. Hamilton, ON (Canada))

1992-12-01

Beryllium is being evaluated for use as a plasma-facing material in the International Thermonuclear Experimental Reactor (ITER). One concern in the evaluation is the retention and permeation of tritium implanted into the plasma-facing surface. We performed laboratory-scale studies to investigate mechanisms that influence hydrogen transport and retention in beryllium foil specimens of rolled powder metallurgy product and rolled ingot cast beryllium. Specimen characterization was accomplished using scanning electron microscopy. Auger electron spectroscopy, and Rutherford backscattering spectrometry (RBS) techniques. Hydrogen transport was investigated using ion-beam permeation experiments and nuclear reaction analysis (NRA). Results indicate that trapping plays a significant role in permeation, re-emission, and retention, and that surface processes at both upstream and downstream surfaces are also important. (orig.).

Characterization of plasma sprayed beryllium ITER first wall mockups

Energy Technology Data Exchange (ETDEWEB)

Castro, R.G.; Vaidya, R.U.; Hollis, K.J. [Los Alamos National Lab., NM (United States). Material Science and Technology Div.

1998-01-01

ITER first wall beryllium mockups, which were fabricated by vacuum plasma spraying the beryllium armor, have survived 3000 thermal fatigue cycles at 1 MW/m{sup 2} without damage during high heat flux testing at the Plasma Materials Test Facility at Sandia National Laboratory in New Mexico. The thermal and mechanical properties of the plasma sprayed beryllium armor have been characterized. Results are reported on the chemical composition of the beryllium armor in the as-deposited condition, the through thickness and normal to the through thickness thermal conductivity and thermal expansion, the four-point bend flexure strength and edge-notch fracture toughness of the beryllium armor, the bond strength between the beryllium armor and the underlying heat sink material, and ultrasonic C-scans of the Be/heat sink interface. (author)

Characterization of Plasma Sprayed Beryllium ITER First Wall Mockups

International Nuclear Information System (INIS)

Castro, Richard G.; Vaidya, Rajendra U.; Hollis, Kendall J.

1997-10-01

ITER first wall beryllium mockups, which were fabricated by vacuum plasma spraying the beryllium armor, have survived 3000 thermal fatigue cycles at 1 MW/sq m without damage during high heat flux testing at the Plasma Materials Test Facility at Sandia National Laboratory in New Mexico. The thermal and mechanical properties of the plasma sprayed beryllium armor have been characterized. Results are reported on the chemical composition of the beryllium armor in the as-deposited condition, the through thickness and normal to the through thickness thermal conductivity and thermal expansion, the four-point bend flexure strength and edge-notch fracture toughness of the beryllium armor, the bond strength between the beryllium armor and the underlying heat sink material, and ultrasonic C-scans of the Be/heat sink interface

Techniques for long term conditioning and storage of radium sources

International Nuclear Information System (INIS)

Dogaru, Gheorghe; Dragolici, Felicia; Nicu, Mihaela

2008-01-01

The Horia Hulubei National Institute of Research and Development for Physics and Nuclear Engineering developed its own technology for conditioning the radium spent sealed radioactive sources. The laboratory dedicated to radiological characterization, identification of radium sources as well as the encapsulation of spent sealed radioactive sources was equipped with a local ventilation system, welding devices, tightness test devices as well as radiometric portable devices. Two types of capsules have been designed for conditioning of radium spent sealed radioactive sources. For these kinds of capsules different types of storage packaging were developed. Data on the radium inventory will be presented in the paper. The paper contains the description of the process of conditioning of spent sealed radioactive sources as well as the description of the capsules and packaging. The paper describes the equipment used for the conditioning of the radium spent sealed sources. (authors)

Implanted Deuterium Retention and Release in Carbon-Coated Beryllium

Science.gov (United States)

Anderl, R. A.; Longhurst, G. R.; Pawelko, R. J.; Oates, M. A.

1997-06-01

Deuterium implantation experiments have been conducted on samples of clean and carbon-coated beryllium. These studies entailed preparation and characterization of beryllium samples coated with carbon thicknesses of 100, 500, and 1000 Å. Heat treatment of a beryllium sample coated with carbon to a thickness of approximately 100 Å revealed that exposure to a temperature of 400°C under high vacuum conditions was sufficient to cause substantial diffusion of beryllium through the carbon layer, resulting in more beryllium than carbon at the surface. Comparable concentrations of carbon and beryllium were observed in the bulk of the coating layer. Higher than expected oxygen levels were observed throughout the coating layer as well. Samples were exposed to deuterium implantation followed by thermal desorption without exposure to air. Differences were observed in deuterium retention and postimplantation release behavior in the carbon-coated samples as compared with bare samples. For comparable implantation conditions (sample temperature of 400°C and an incident deuterium flux of approximately 6 × 1019 D/m2-s), the quantity of deuterium retained in the bare sample was less than that retained in the carbon-coated samples. Further, the release of the deuterium took place at lower temperatures for the bare beryllium surfaces than for carbon-coated beryllium samples.

Health risk assessment for radium discharged in produced waters

International Nuclear Information System (INIS)

Hamilton, L.D.; Meinhold, A.F.; Nagy, J.

1991-01-01

Produced water generated during the production of oil and gas can contain enhanced levels of radium. This naturally occurring radioactive material (NORM) is discharged into freshwater streams, estuarine, coastal and outer continental shelf waters. Large volumes of produced waters are discharged to coastal waters along the Gulf Coast of Louisiana. The Gulf of Mexico is an important producer of fish and shellfish, and there is concern that radium discharged to coastal Louisiana could contaminate fish and shellfish used by people for food, and present a significant increase in cancer risk. This paper describes a screening-level assessment of the potential cancer risks posed by radium discharged to coastal Louisiana in oil-field produced waters. This screening analysis was performed to determine if a more comprehensive and realistic assessment is necessary, and because of the conservative assumptions embedded in the analysis overestimates the risk associated with the discharge of radium in produced waters. Two isotopes of radium (Ra-226 and Ra-228) are the radionuclides of most concern in produced water in terms of potential human health effects

Radium-bearing waters in the Upper Silesian Coal Basin

International Nuclear Information System (INIS)

Tomza, I.; Lebecka, J.; Pluta, I.

1986-01-01

Natural waters with a high radium content occuring in underground workings of coal mines in Upper Silesia are described. Above 1500 water samples from carbonifereous aquifers were taken and the concentration of 226 Ra was measured. In about 100 samples also uranium was determined. The 226 Ra concentration varied in a wide range from 0.01 kBq/m 3 to 270 kBq/m 3 , while the uranium content was usually much lower than one could expect from the equilibrium between radium and uranium. It was observed that the 226 Ra concentration increases with mineralization of water, however the correlation was rather poor. Two types of radium-bearing waters were distinguished. Waters type A - containing Ba 2+ ions and waters type B - containing SO 4 2- ions. Waters type A are always reach in radium and usually have higher concentration of 226 Ra than waters type B. The described waters have one of the highest radium concentration which have been found so far in the natural environment. (author)

MEASUREMENTS OF THE PROPERTIES OF BERYLLIUM FOIL

International Nuclear Information System (INIS)

ZHAO, Y.; WANG, H.

2000-01-01

The electrical conductivity of beryllium at radio frequency (800 MHz) and liquid nitrogen temperature were investigated and measured. This summary addresses a collection of beryllium properties in the literature, an analysis of the anomalous skin effect, the test model, the experimental setup and improvements, MAFIA simulations, the measurement results and data analyses. The final results show that the conductivity of beryllium is not as good as indicated by the handbook, yet very close to copper at liquid nitrogen temperature

Study of possible economical ways of removing radium from drinking water

International Nuclear Information System (INIS)

Valentine, R.L.; Splinter, R.C.; Mulholland, T.S.; Baker, J.M.; Nogaj, T.M.

1988-01-01

This study was undertaken to determine variables that control the incidental removal of radium that has been observed to occur as a consequence of treatment to remove iron by oxidation--sand filtration. The study also evaluated the possibility of exploiting these factors to provide an inexpensive means of removing radium using existing or modified iron removal facilities. Studies were also conducted to evaluate radium sorption to hydrous manganese oxides and to evaluate the potential of radium sorption to filter sand as a novel removal technology. Results showed that radium sorption to iron and manganese oxides and filter sand appear to be controlled primarily by the presence of calcium and magnesium, which are believed to compete for sorption sites

Field measurements of radium in the human body

International Nuclear Information System (INIS)

Toohey, R.E.; May, H.A.

1978-01-01

Two whole body counting systems have been developed and employed for field measurements. The radium contents of nine previously unmeasured cases have been determined during three field trips. Future trips are being scheduled to make body radioactivity measurements on a specific subpopulation of CHR radium cases

Principal aquifers can contribute radium to sources of drinking water under certain geochemical conditions

Science.gov (United States)

Szabo, Zoltan; Fischer, Jeffrey M.; Hancock, Tracy Connell

2012-01-01

What are the most important factors affecting dissolved radium concentrations in principal aquifers used for drinking water in the United States? Study results reveal where radium was detected and how rock type and chemical processes control radium occurrence. Knowledge of the geochemical conditions may help water-resource managers anticipate where radium may be elevated in groundwater and minimize exposure to radium, which contributes to cancer risk. Summary of Major Findings: * Concentrations of radium in principal aquifers used for drinking water throughout the United States generally were below 5 picocuries per liter (pCi/L), the U.S. Environmental Protection Agency (USEPA) maximum contaminant level (MCL) for combined radium - radium-226 (Ra-226) plus radium-228 (Ra-228) - in public water supplies. About 3 percent of sampled wells had combined radium concentrations greater than the MCL. * Elevated concentrations of combined radium were more common in groundwater in the eastern and central United States than in other regions of the Nation. About 98 percent of the wells that contained combined radium at concentrations greater than the MCL were east of the High Plains. * The highest concentrations of combined radium were in the Mid-Continent and Ozark Plateau Cambro-Ordovician aquifer system and the Northern Atlantic Coastal Plain aquifer system. More than 20 percent of sampled wells in these aquifers had combined radium concentrations that were greater than or equal to the MCL. * Concentrations of Ra-226 correlated with those of Ra-228. Radium-226 and Ra-228 occur most frequently together in unconsolidated sand aquifers, and their presence is strongly linked to groundwater chemistry. * Three common geochemical factors are associated with the highest radium concentrations in groundwater: (1) oxygen-poor water, (2) acidic conditions (low pH), and (3) high concentrations of dissolved solids.

Moderator for nuclear reactor

International Nuclear Information System (INIS)

Milgram, M.S.; Dunn, J.T.; Hart, R.S.

1995-01-01

This invention relates to a moderator for a nuclear reactor and more specifically, to a composite moderator. A moderator is designed to slow down, or thermalize, neutrons which are released during nuclear reactions in the reactor fuel. Pure or almost pure materials like light water, heavy water, beryllium or graphite are used singly as moderators at present. All these materials, are used widely. Graphite has a good mechanical strength at high temperatures encountered in the nuclear core and therefore is used as both the moderator and core structural material. It also exhibits a low neutron-capture cross section and high neutron scattering cross section. However, graphite is susceptible to attach by carbon dioxide and/or oxygen where applicable, and releases stress energy under certain circumstances, although under normal operating conditions these reactions can be controlled. (author). 1 tab

Preparation of a sinterable beryllium oxide through decomposition of beryllium hydroxide (1963)

International Nuclear Information System (INIS)

Bernier, M.

1963-01-01

In the course of the present study, we have attempted to precise the factors which among the ones effective in the course of the preparation of the beryllium hydroxide and oxide and during the sintering have an influence on the final result: the density and homogeneity of the sintered body. Of the several varieties of hydroxides precipitated from a sulfate solution the β-hydroxide only is always contaminated with beryllium sulfate and cannot be purified even by thorough washing. We noticed that those varieties of the hydroxide (gel, α, β) have different decomposition rates; this behaviour is used to identify and even to dose the different species in (α, β) mixtures. The various hydroxides transmit to the resulting oxides the shape they had when precipitated. Accordingly the history of the oxide is revealed by its behaviour during its fabrication and sintering. By comparing the results of the sintering operation with the various measurements performed on the oxide powders we are led to the conclusion that an oxide obtained from beryllium hydroxide is sinterable under vacuum if the following conditions are fulfilled: the particle size must lie between 0.1 and 0.2 μ and the BeSO 4 content of the powder must be less than 0.25 per cent wt (expressed as SO 3 /BeO). The best fitting is obtained with the oxide issued from an α-hydroxide precipitated as very small aggregates and with a low sulfur-content. We have observed that this is also the case for the oxide obtained by direct calcination of beryllium sulfate. (author) [fr

Reference moderator calculated performance for the LANSCE upgrade project

International Nuclear Information System (INIS)

Ferguson, P.D.; Russell, G.J.; Pitcher, E.J.

1995-01-01

The authors have calculated the performance of five moderators of interest to the LANSCE upgrade project. Coupled and decoupled light water and liquid hydrogen moderators in flux-trap geometry surrounded by a neutronically infinite heavy-water cooled beryllium reflector have been studied. Time and energy spectra, as well as semi-empirical fits to the data, are presented. The data has been made available to aid the instrument design and moderator selection process

Beryllium poisonings

International Nuclear Information System (INIS)

Alibert, S.

1959-03-01

This note reports a bibliographical study of beryllium toxicity. Thus, this bibliographical review addresses and outlines aspects and issues like aetiology, cases of acute poisoning (cutaneous manifestations, pulmonary manifestations), chronic poisoning (cutaneous, pulmonary and bone manifestations), excretion and localisation, and prognosis

Thermogravimetric analysis of the beryllium/steam reaction

Energy Technology Data Exchange (ETDEWEB)

Druyts, Frank E-mail: fdruyts@sckcen.be; Iseghem, Pierre van

2000-11-01

In view of the safety assessment of new fusion reactor designs, kinetic data are needed on the beryllium/steam reaction. Therefore, thermogravimetric analysis was used to determine the reactivity of beryllium in steam as a function of temperature, irradiation history and porosity of the samples. To this purpose, reference unirradiated S-200 VHP beryllium samples were compared with specimens irradiated in the BR2 reactor up to fast neutron fluences (E>1 MeV) of respectively 1.6x10{sup 21} n cm{sup -2} (resulting in a helium content of 300 appm He and a theoretical density of 99.9%) and 4x10{sup 22} n cm{sup -2} (21000 appm He, 97.2% theoretical density). Kinetics were parabolic for all tested beryllium types at 600 deg. C. At 700 deg. C, kinetics were parabolic for the unirradiated and irradiated 99.9% dense beryllium, and accelerating/linear for the irradiated 97.2% material. At 800 deg. C, all samples showed accelerating/linear behaviour. There was no influence of porosity on the reaction rate of beryllium in steam within the limited investigated density range, except at 700 deg. C, where the measured reaction rate for the irradiated 97.2% dense samples is an order of magnitude higher than for the irradiated 99.9% dense specimens.

Tritium release from neutron irradiated beryllium pebbles

Energy Technology Data Exchange (ETDEWEB)

Scaffidi-Argentina, F.; Werle, H. [Forschungszentrum Karlsruhe GmbH Technik und Umwelt (Germany). Inst. fuer Neutronenphysik und Reactortechnik

1998-01-01

One of the most important open issues related to beryllium for fusion applications refers to the kinetics of the tritium release as a function of neutron fluence and temperature. The EXOTIC-7 as well as the `Beryllium` experiments carried out in the HFR reactor in Petten are considered as the most detailed and significant tests for investigating the beryllium response under neutron irradiation. This paper reviews the present status of beryllium post-irradiation examinations performed at the Forschungszentrum Karlsruhe with samples from the above mentioned irradiation experiments, trying to elucidate the tritium release controlling processes. In agreement with previous studies it has been found that release starts at about 500-550degC and achieves a maximum at about 700-750degC. The observed release at about 500-550degC is probably due to tritium escaping from chemical traps, while the maximum release at about 700-750degC is due to tritium escaping from physical traps. The consequences of a direct contact between beryllium and ceramics during irradiation, causing tritium implanting in a surface layer of beryllium up to a depth of about 40 mm and leading to an additional inventory which is usually several times larger than the neutron-produced one, are also presented and the effects on the tritium release are discussed. (author)

Reverse osmosis separation of radium from dilute aqueous solutions

International Nuclear Information System (INIS)

Subramanian, K.S.; Sastri, V.S.

1980-01-01

Porous cellulose acetate membranes obtained from Osmonics Inc. were characterized in terms of pure water permeability constant, solute transport parameter, and mass transfer coefficient with aqueous sodium chloride solution as the reference system. Reverse osmosis separation behavior of radium-226 as nitrate, chloride, and sulfate salts was studied. Reverse osmosis method of removing radium-226 from aqueous solutions has been compared with other methods, and it has been shown to be one of the best methods for alleviating radium contamination problems

Bone sarcoma induction by radium 224 in C57BL/Do mice

International Nuclear Information System (INIS)

Mays, C.W.; Lloyd, R.D.; Taylor, G.N.; Jones, C.W.

1989-01-01

Ninety-five C57BL/Do mice received radium 224 in ten weekly intraperitoneal injections. Doses ranged from 0.5 to 11.6 Gy. Twelve mice developed bone sarcoma. The risk coefficient ±SD was 2.8 ± 0.8%/Gy and the toxicity of shortlived radium 224 relative to longlived radium 226 was 5.4 ± 2.0. Concurrently, a single injection of 33 kBq/kg plutonium 239 was given to 47 similar mice which had a bone sarcoma risk coefficient of 8.4 ± 0.8%/Gy and toxicity relative to longlived radium 226 of 16 ± 4. Based on the studies of Mueller et al that established the increase in effectiveness with increased protraction of radium 224 dose, it is possible, if the radium 224 total dose had been spread continually over about 1 year, that the toxicity of the radium 224 might have been similar to that of plutonium 239. (author)

Reflector drums as control mechanism for craft thermionic reactors with constant emitter heating containing U-233 as fuel and beryllium as moderator

International Nuclear Information System (INIS)

Sahin, S.; Selvi, S.

1980-01-01

The suitability of borated reflector drums has been investigated and shown as a control mechanism for space craft thermionic reactors with constant emitter heating using U-233 as fuel and beryllium to be moderator, mainly due to their extremce compactness and their very soft neutron sepctrum. The achievable change in ksub(eff) allows long-term control operation with success. The use of reflector drums keeps the cone diameter and the mass of the radiation shield on minimum. The distortion of the emitter heating field remains under acceptable tolerances, mainly due to the enhanced neutron production at the outer core region and the remaining reflector part between the boron layer and the core. All neutron physics calculations have been carried out using the multigroup Ssub(N) methods. Three data groups for r-theta-calculations in S 4 -P 1 approximation (16 space angles) have been evaluated from a 123-energy-groups data library using transport theoretical methods. (orig.) [de

Long term consumption of mineral spring water containing natural radium-226

International Nuclear Information System (INIS)

Aulenbach, D.B.; Davis, R.E.

1976-01-01

The presence of naturally occurring 226 radium in several of the spring waters of Saratoga Springs, New York has been known for some time. However, recently the recommended maximum acceptable limit for consumption of water containing radium has been lowered to the point that the limits are now lower than the concentration of radium observed in several of the wells. A survey was made of 27 individuals who have consumed water from the Hathorn No. 1 Spring for periods varying from 5-65 years. A calculation was made of the 226 radium body burden from equations provided in the literature. The calcium concentration of the springs was determined in consideration of the still unknown comparative selectivity of the body between radium and calcium. Waters from two of the springs were analzyed for 226 radium using the radon emanation method. No adverse effects of consuming the mineral water were observed in the individuals interviewed nor were there any increased incidences of broken or brittle bones among these individuals

Health consequences of nasopharyngeal radium exposure

International Nuclear Information System (INIS)

Sandler, D.P.; Matanoski, G.; Comstock, G.W.; Mitchell, T.

1980-01-01

The study was undertaken to determine whether a population of children with hearing loss who were irradiated with radium applicators in the forties and fifties would have an increased risk of tumors in the area of the nasopharynx, thyroid, and other surrounding tissues or would have other long-term results of radium treatments such as signs of hormonal changes related to radiation exposure of the pituitary glands. The results of the study of the chronic effects from irradiation of adenoids suggests a significant excess risk of head and neck cancers, especially brain tumors. The increased incidence of thyrotoxicosis in the exposed population may have resulted from hormonal imbalance secondary to pituitary gland irradiation and should receive further study. Chronic hearing loss occurred more frequently in the irradiated group but it is difficult to be sure whether this indicated an ineffectiveness of the treatment or differences in the characteristics of the deafness in individuals selected for radium treatments

Remediation of soil/concrete contaminated with uranium and radium by biological method

International Nuclear Information System (INIS)

Gye-Nam Kim; Seung-Su Kim; Hye-Min Park; Won-Suk Kim; Uk-Ryang Park; Jei-Kwon Moon

2013-01-01

Biological method was studied for remediation of soil/concrete contaminated with uranium and radium. Optimum experiment conditions for mixing ratios of penatron and soil, and the pH of soil was obtained through several bioremediations with soil contaminated with uranium and radium. It was found that an optimum mixing ratio of penatron for bioremediation of uranium soil was 1 %. Also, the optimum pH condition for bioremediation of soil contaminated with uranium and radium was 7.5. The removal efficiencies of uranium and radium from higher concentration of soil were rather reduced in comparison with those from lower concentration of soil. Meanwhile, the removal of uranium and radium in concrete by bioremediation is possible but the removal rate from concrete was slower than that from soil. The removal efficiencies of uranium and radium from soil under injection of 1 % penatron at pH 7.5 for 120 days were 81.2 and 81.6 %, respectively, and the removal efficiencies of uranium and radium from concrete under the same condition were 63.0 and 45.2 %, respectively. Beyond 30 days, removal rates of uranium and radium from soil and concrete by bioremediation was very slow. (author)

Effect of machining damage on tensile properties of beryllium

International Nuclear Information System (INIS)

Hanafee, J.E.

1976-01-01

It is well established that damage introduced at the surface of beryllium during machining operations can lower its mechanical properties. Tensile tests were conducted to illustrate this on beryllium presently being used for parts in the W79 program and similar to the new powder-processed beryllium specified for production (tentative specification MEL 76-001319). The objective of this study is to quantitatively illuminate the importance of controlling machining damage in this particular grade of powder-processed beryllium

Sintering of beryllium oxide

International Nuclear Information System (INIS)

Caillat, R.; Pointud, R.

1955-01-01

This study had for origin to find a process permitting to manufacture bricks of beryllium oxide of pure nuclear grade, with a density as elevated as possible and with standardized shape. The sintering under load was the technique kept for the manufacture of the bricks. Because of the important toxicity of the beryllium oxide, the general features for the preliminary study of the sintering, have been determined while using alumina. The obtained results will be able to act as general indication for ulterior studies with sintering under load. (M.B.) [fr

Radium and thorium with barium in micronodules of cattle thyroids

International Nuclear Information System (INIS)

Van Middlesworth, L.

1980-01-01

Radium isotopes were found concentrated in thyroid glands of cattle. The incidence of measurable radium varied from 80% to less than 0.1% in thyroids from different abattoirs. The radium was concentrated in microscopic bodies containing predominantly barium and sulfur and lying within the storage of thyroglobulin, adjacent to follicular cells. Some thyroid cells may receive biologically significant doses of alpha radiation from these sources

Managing health effects of beryllium exposure

National Research Council Canada - National Science Library

Committee on Beryllium Alloy Exposures; Committee on Toxicology; National Research Council; Division on Earth and Life Studies; National Research Council

2008-01-01

... to its occurrence in exposed people. Despite reduced workplace exposure, chronic beryllium disease continues to occur. In addition, beryllium has been classified as a likely human carcinogen by several agencies, such as the International Agency for Research on Cancer, the National Toxicology Program, and the U.S. Environmental Protection Agency. Thos...

Process for the removal of radium from acidic solutions containing same

International Nuclear Information System (INIS)

Scheitlin, F.M.

1984-01-01

Radium is removed from an inorganic-acid solution contacting the solution with coal fly ash to effect adsorption of the radium on the ash. The radium-containing ash then is separated from the solution. The process is simple and efficient. High radium-distribution coefficients are obtained even at room temperature. Coal fly ash is an inexpensive, acid-resistant, high-surface-area material which is available in large quantities. The invention is applicable, for example, to the recovery of 226 Ra from nitric acid solutions which have been used to leach radium from uranium-mill tailings, and thus contain thorium and uranium. The contaminated fly ash may be incorporated in a suitable matrix and stored, and the residual solutions processed to separate uranium and thorium. (author)

Implanted deuterium retention and release in carbon-coated beryllium

International Nuclear Information System (INIS)

Anderl, R.A.; Longhurst, G.R.; Pawelko, R.J.; Oates, M.A.

1997-01-01

Deuterium implantation experiments have been conducted on samples of clean and carbon-coated beryllium. These studies entailed preparation and characterization of beryllium samples coated with carbon thicknesses of 100, 500, and 1000 angstrom. Heat treatment of a beryllium sample coated with carbon to a thickness of approximately 100 angstrom revealed that exposure to a temperature of 400 degrees C under high vacuum conditions was sufficient to cause substantial diffusion of beryllium through the carbon layer, resulting in more beryllium than carbon at the surface. Comparable concentrations of carbon and beryllium were observed in the bulk of the coating layer. Higher than expected oxygen levels were observed throughout the coating layer as well. Samples were exposed to deuterium implantation followed by thermal desorption without exposure to air. Differences were observed in deuterium retention and postimplantation release behavior in the carbon-coated samples as compared with bare samples. For comparable implantation conditions (sample temperature of 400 degrees C and an incident deuterium flux of approximately 6 X 10 19 D/m 2 sec), the quantity of deuterium retained in the bare sample was less than that retained in the carbon-coated samples. Further, the release of the deuterium took place at lower temperatures for the bare beryllium surfaces than for carbon-coated beryllium samples. 4 refs., 8 figs., 1 tab

Radiation exposure from radium-226 ingestion

International Nuclear Information System (INIS)

Keefer, D.H.; Fenyves, E.J.

1980-01-01

The contribution of radium to total radiation exposure resulting from the consumption of natural levels of 226 Ra in several public water supplies in an Oklahoma county was determined. A pilot-level study of total dietary intake indicated that the culinary use of water anomalously high in radium and the consumption of water-based beverages contributed significantly to radiation exposure. The mean dietary intake of 226 Ra was 20.6 pCi/day in one community and resulted in an estimated bone dose of 310 mrem/year

Beryllium in aircraft brakes - a summary

International Nuclear Information System (INIS)

Zenczak, S.

1977-01-01

Beryllium has been in use in aircraft brakes for ten years. During the original design phases of the several aircraft programs using beryllium a number of problems requiring solution confronted the designers. In actual service the solution to these problems performed much better than had been anticipated. A summary is presented. (author)

Galvanic corrosion of beryllium welds

International Nuclear Information System (INIS)

Hill, M.A.; Butt, D.P.; Lillard, R.S.

1997-01-01

Beryllium is difficult to weld because it is highly susceptible to cracking. The most commonly used filler metal in beryllium welds is Al-12 wt.% Si. Beryllium has been successfully welded using Al-Si filler metal with more than 30 wt.% Al. This filler creates an aluminum-rich fusion zone with a low melting point that tends to backfill cracks. Drawbacks to adding a filler metal include a reduction in service temperature, a lowering of the tensile strength of the weld, and the possibility for galvanic corrosion to occur at the weld. To evaluate the degree of interaction between Be and Al-Si in an actual weld, sections from a mock beryllium weldment were exposed to 0.1 M Cl - solution. Results indicate that the galvanic couple between Be and the Al-Si weld material results in the cathodic protection of the weld and of the anodic dissolution of the bulk Be material. While the cathodic protection of Al is generally inefficient, the high anodic dissolution rate of the bulk Be during pitting corrosion combined with the insulating properties of the Be oxide afford some protection of the Al-Si weld material. Although dissolution of the Be precipitate in the weld material does occur, no corrosion of the Al-Si matrix was observed

Distribution of radium in oil and gas industry wastes from Malaysia

International Nuclear Information System (INIS)

Omar, M.; Ali, H.M.; Abu, M.P.; Kontol, K.M.; Ahmad, Z.; Ahmad, S.H.S.S.; Sulaiman, I.; Hamzah, R.

2004-01-01

Radium concentrations in 470 samples of the various types of waste from oil and gas industries were analysed using gamma spectrometers. The results showed that the radium concentration varied within a wide range. The highest mean 226 Ra and 228 Ra concentrations of 114,300 and 130,120 Bq/kg, respectively, were measured in scales. Overall, 75% of the waste, mostly sludge and extraction residue lies within the normal range of radium concentration in soils of Malaysia. However, some platform sludge can have radium concentration up to 560 Bq/kg

Distribution of radium in oil and gas industry wastes from Malaysia.

Science.gov (United States)

Omar, M; Ali, H M; Abu, M P; Kontol, K M; Ahmad, Z; Ahmad, S H S S; Sulaiman, I; Hamzah, R

2004-05-01

Radium concentrations in 470 samples of the various types of waste from oil and gas industries were analysed using gamma spectrometers. The results showed that the radium concentration varied within a wide range. The highest mean 226Ra and 228Ra concentrations of 114,300 and 130,120 Bq/kg, respectively, were measured in scales. Overall, 75% of the waste, mostly sludge and extraction residue lies within the normal range of radium concentration in soils of Malaysia. However, some platform sludge can have radium concentration up to 560 Bq/kg.

Status of material development for lifetime expansion of beryllium reflector

Energy Technology Data Exchange (ETDEWEB)

Dorn, C [Materion Brush Beryllium and Composites, California (United States); Tsuchiya, Kunihiko; Kawamura, Hiroshi [Japan Atomic Energy Agency, Oarai Research and Development Center, Oarai, Ibaraki (Japan); Hatano, Y [Univ. of Toyama, Toyama (Japan); Chakrov, P [INP-KNNC, Almaty (Kazakhstan); Kodama, M [Nippon Nuclear Fuel Development Co., Ltd., Oarai, Ibaraki (Japan)

2012-03-15

Beryllium has been used as the reflector element material in the reactor, specifically S-200F structural grade beryllium manufactured by Materion Brush Beryllium and Composites (former, Brush Wellman Inc.). As a part of the reactor upgrade, the Japan Atomic Energy Agency (JAEA) also has carried out the cooperation experiments to extend the operating lifetime of the beryllium reflector elements. It will first be necessary to determine which of the material's physical, mechanical and chemical properties will be the most influential on that choice. The irradiation testing plans to evaluate the various beryllium grades are also briefly considered and prepared. In this paper, material selection, irradiation test plan and PEI development for lifetime expansion of beryllium are described for material testing reactors. (author)

Improved method for the determination of dissolved radium-226

International Nuclear Information System (INIS)

Yang, I.C.

1984-01-01

Most of the current techniques for radium determination involve chemical separation of radium from major sample constituents by coprecipitation with barium or lead sulfate, followed by further radium purification. However, when samples contain biological materials, such as algae in wastewater from uranium millponds, or brine water from oil fields, the precipitation and purification processes become tedious and time-consuming. An improved method has been developed for the determination of radium-226 in such water samples, which also is applicable to natural waters. This method is based on a radon determination of alpha activity of the radon and its short-lived daughters in an alpha-scintillation cell. The radon-bubbler volume is either 90 millimeters for concentrated samples or 800 milliliters for dilute samples. For radium concentrations less than 1 picocurie per liter, 2 liters of water sample can be concentrated several-fold by simple evaporation, and decreased to 800 milliliters prior to deemanation. Because the process involves no chemical separations, chemical recoveries are nearly 100 percent. The lower limit of detection is 0.05 picocurie per liter for a 1-liter water sample and a counting time of 1000 minutes. 19 references, 3 figures, 3 tables

Experiments on tritium behavior in beryllium, (1)

International Nuclear Information System (INIS)

Kawamura, Hiroshi; Ishizuka, Etsuo; Matsumoto, Mikio; Inada, Seiji; Sezaki, Katsuji; Saito, Minoru; Kato, Mineo.

1989-06-01

In JMTR, it was observed that the tritium concentration of the primary coolant increases with the reactor operation at 50 MW. As one of the tritium generation sources, we paid attention to a neutron reflector made of beryllium because the tritium generation rate in the beryllium is bigger than other components in the reactor core. On the other hand, the irradiation test of blanket materials (i.e. tritium breeding materials and neutron multipling materials) are planned for development of the fusion reactor in JMTR and the beryllium will be also irradiated as a neutron multiplier with tritium breeding materials. Therefore, as the irradiated specimens, we used a hot-pressed beryllium disk fabricated by the same method as the neutron reflector or the neutron multiplier and conducted the irradiation tests in JMTR. The purpose of these tests are to clarify the tritium behavior in the hot-pressed beryllium. In this paper, from a viewpoint of the fabrication of capsules for neutron irradiation, the specifications of the irradiated specimens and capsules are summarized. Additionally, the results on the puncture test of the container of the irradiation specimens are described. (author)

Structure investigations of some beryllium materials

Energy Technology Data Exchange (ETDEWEB)

Faeldt, I; Lagerberg, G

1960-05-15

Metallographic structure, microhardness and texture have been studied on various types of beryllium metal including hot pressed powder, a rolled strip and an extruded tube It was found that beryllium exhibits its highest hardness in directions perpendicular to the basal plane. Good ideas of the prevailing textures were obtained with an ordinary X-ray diffractometer.

Structure investigations of some beryllium materials

International Nuclear Information System (INIS)

Faeldt, I.; Lagerberg, G.

1960-05-01

Metallographic structure, microhardness and texture have been studied on various types of beryllium metal including hot pressed powder, a rolled strip and an extruded tube It was found that beryllium exhibits its highest hardness in directions perpendicular to the basal plane. Good ideas of the prevailing textures were obtained with an ordinary X-ray diffractometer

The adhesive bonding of beryllium structural components

International Nuclear Information System (INIS)

Fullerton-Batten, R.C.

1977-01-01

Where service conditions permit, adhesive bonding is a highly recommendable, reliable means of joining beryllium structural parts. Several important programs have successfully used adhesive bonding for joining structural and non-structural beryllium components. Adhesive bonding minimizes stress concentrations associated with other joining techniques and considerably improves fatigue resistance. In addition, no degradation of base metal properties occur. In many instances, structural joints can be fabricated more cheaply by adhesive bonding or in combination with adhesive bonding than by any other method used alone. An evaluation program on structural adhesive bonding of beryllium sheet components is described. A suitable surface pretreatment for beryllium adherends prior to bonding is given. Tensile shear strength and fatigue properties of FM 1000 and FM 123-5 adhesive bonded joints are reviewed and compared with data obtained from riveted joints of similar geometry. (author)

Beryllium armour produced by evaporation-condensation technique

International Nuclear Information System (INIS)

Anisimov, A.; Frolov, V.; Moszherin, S.; Pepekin, G.; Pirogov, A.; Komarov, V.; Mazul, I.

1997-01-01

Beryllium, as armour material for ITER plasma facing components, has a limited erosion lifetime. In order to repair the surface of eroded tiles in-situ, Be-deposition technologies are under consideration. One of them uses the physical vapour deposition of beryllium on copper or beryllium substrate produced by a hot Be-target placed in the vicinity of this substrate. Three different options for using this technology for ITER Be-armour application are considered. The first option is the repair in-situ of eroded Be-tiles. The second option suggests the use of this technology to provide the joining of Be to Cu-substrate. The third option assumes the use of evaporated-condensed beryllium as a bulk tile material bonded to copper substrate by conventional joining (Brazing et al.) techniques. The first results and prospects of these approaches are presented below. (orig.)

Experiments on tritium behavior in beryllium, (2)

International Nuclear Information System (INIS)

Ishitsuka, Etsuo; Kawamura, Hiroshi; Nakata, Hirokatsu; Sugai, Hiroyuki; Tanase, Masakazu.

1990-02-01

Beryllium has been used as the neutron reflector of material testing reactor and as the neutron multiplier for the fusion reactor lately. To study the tritium behavior in beryllium, we conducted the experiments, i.e., tritium release by recoil or diffusion by using the hot-pressed beryllium which had been produced both tritium and helium by neutron irradiation. From our experiments, we found that (1) amount of tritium production per one cycle irradiation (lasting 22 days) of JMTR is 10 mCi/g, (2) amount of tritium per surface area of hot-pressed beryllium released by recoil is 4 μCi/cm 2 , (3) diffusion coefficient of tritium in a temperature range of 800 ∼1180degC can be expressed with the following equation; D = 8.7 x 10 4 exp(-2.9x10 5 /R/T) cm 2 /s. (author)

Physico-chemical forms and migration in continental waters of radium from uranium mining and milling

International Nuclear Information System (INIS)

Benes, P.

1982-01-01

Recent advances in knowledge of the physico-chemical forms and migration of radium in continental waters are reviewed and recommendations for future research in this field are given. Computations of solution equilibria based on the reported and newly determined stability constants and solubilities of radium compounds show that a significant percentage of dissolved radium can exist in some waste and natural waters as an RaSO 4 ion pair, besides a significant percentage of Ra 2+ ions. The formation of a solid phase consisting mainly of sparingly soluble radium compounds can be excluded in waste and natural waters. Model experiments revealed that radium can be bound in complexes with some as yet unidentified ligands, probably of organic nature. Direct determinations of the physico-chemical forms of radium in surface and groundwaters were mostly confined to the analysis of the ratio of dissolved to particulate forms of radium. Ratios from 0.01 to 100 were found, depending on the type of water examined. Recently a newly suggested method of selective dissolution was applied to characterize the nature of particulate forms of radium in surface waters. Migration of radium is reviewed, covering the release of radium from its source, its transport in ground and surface waters and its deposition in various sinks. Factors influencing radium release from the sources into the hydrosphere are discussed. The following processes affecting radium migration are discussed: adsorption of dissolved radium on suspended solids and bottom sediments, coprecipitation of radium with solids formed in waste waters or in natural waters, sedimentation of particulate forms of radium in reservoirs and streams, resuspension of bottom sediments and dissolution of radium from suspended solids or bottom sediments

Assessment of the feasibility and advantages of beryllium recycling

International Nuclear Information System (INIS)

Druyts, F.; Braet, J.; Ooms, L.

2006-01-01

This paper proposes a generic route for the recycling of beryllium from fusion reactors, based on critical issues associated with beryllium pebbles after their service life in the HCPB breeding blanket. These critical issues are the high tritium inventory, the presence of long-lived radionuclides (among which transuranics due to traces of uranium in the base metal), and the chemical toxicity of beryllium. On the basis of the chemical and radiochemical characteristics of the neutron irradiated beryllium pebbles, we describe a possible recycling route. The first step is the detritiation of the material. This can be achieved by heating the pebbles to 800 o C under an argon flow. The argon gas avoids oxidation of the beryllium, and at the proposed temperature the tritium inventory is readily released from the pebbles. In a second step, the released tritium can be oxidised on a copper oxide bed to produce tritiated water, which is consistent with the current international strategy to convert all kinds of tritiated waste into tritiated water, which can subsequently be treated in a water detritiation plant. Removal of radionuclides from the beryllium pebbles may be achieved by several types of chloride processes. The first step is to pass chlorine gas (in an argon flow) over the pebbles, thus yielding volatile BeCl 2 . This beryllium chloride can then be purified by fractional distillation. As a small fraction of the beryllium chloride contains the long-lived 10 Be isotope, 10BeCl 2 has to be separated from 9BeCl 2 , which could be achieved by centrifugal techniques. The product can then be reduced to obtain high-purity metallic beryllium. Two candidate reduction methods were identified: fused salt electrolysis and thermal decomposition. Both these methods require laboratory parametric studies to maximise the yield and achieve a high purity metal, before either process can be upgraded to a larger scale. The eventual product of the chloride reduction process must be a high

The influence of radium therapie on the yeast contamination of the vagina

International Nuclear Information System (INIS)

Mendling, W.; Schnell, J.D.; Spiecker, R.; Sankt Franziskus-Hospital, Bielefeld

1979-01-01

Before the beginning of radium therapy a vaginal yeast contamination of 9,7% was found of 113 patients with various genital carcinomas. However, the incidence of vaginal yeast contamination increased suddenly to 30,9% under the contac irradiation therapy with radium. The radiation effect of radium is not sufficient for a 'selfsterilisation' of the radium-carrier in the case of yeast contamination. Therefore, a chemic desinfection of the radium-carriers is principly necessary. The significance is discussed and the recommendation is made that routine mycological supervision be carried out on all patients with gynaecological carcinomas and appropriate antimycotic therapy initiated where necessary. (orig.) [de

Metallurgical viewpoints on the brittleness of beryllium

Energy Technology Data Exchange (ETDEWEB)

Lagerberg, G

1960-02-15

At present the development and use of beryllium metal for structural applications is severely hampered by its brittleness. Reasons for this lack of ductility are reviewed in discussing the deformation behaviour of beryllium in relation to other hexagonal metals. The ease of fracturing in beryllium is assumed to be a consequence of a limited number of deformation modes in combination with high deformation resistance. Models for the nucleation of fracture are suggested. The relation of ductility to elastic constants as well as to grain size, texture and alloying additions is discussed.

Metallurgical viewpoints on the brittleness of beryllium

International Nuclear Information System (INIS)

Lagerberg, G.

1960-02-01

At present the development and use of beryllium metal for structural applications is severely hampered by its brittleness. Reasons for this lack of ductility are reviewed in discussing the deformation behaviour of beryllium in relation to other hexagonal metals. The ease of fracturing in beryllium is assumed to be a consequence of a limited number of deformation modes in combination with high deformation resistance. Models for the nucleation of fracture are suggested. The relation of ductility to elastic constants as well as to grain size, texture and alloying additions is discussed

Radiobiological Parameters in Human Cancers Attributable to Long-Term Radium Deposition

Energy Technology Data Exchange (ETDEWEB)

Finkel, A. J.; Miller, C. E.; Hasterlik, R. J. [Argonne National Laboratory, Argonne, IL (United States); Argonne Cancer Research Hospital, Chicago, IL (United States)

1969-11-15

A mixed population of about 300 persons that acquired appreciable body burdens of radium 35 to 50 years ago has been followed by our group for the past 20 years. Radium was acquired by these patients by occupational exposure and from administration orally and intravenously by their physicians. To date, a number of these patients have developed fibrosarcomas and osteogenic sarcomas of skeletal tissues, carcinomas and sarcomas of the mastoids and paranasal sinuses, and serious blood dyscrasias. In many cases, analysis of the exposure history and of contemporary, body burdens has enabled us to reconstruct the patterns of radium retention. From these computations, we have been able to analyse the appearance of neoplasms in terms of: (1) contemporary or terminal radium burdens, (2) estimated maximum (i.e. peak initial) radium burdens, and (3) estimated daily and total amounts of radium entering the blood stream during exposure. The ranges of values of these various indices for groups of patients with and without malignant disease and other disabling conditions may serve to characterize the likelihood of radiation carcinogenesis in these and similar patients. (author)

Laser welding of a beryllium/tantalum collimator

International Nuclear Information System (INIS)

Lingenfelter, A.C.; Anglin, C.D.

1985-01-01

This report describes the methods utilized in the fabrication of a collimator from 0.001 inch thick beryllium and tantalum foil. The laser welding process proved to be an acceptable method for joining the beryllium in a standing edge joint configuration

Survey of medical radium installations in Wisconsin

International Nuclear Information System (INIS)

Tapert, A.C.; Lea, W.L.

1975-05-01

A radiation protection survey was performed at 70 medical radium installations in the State of Wisconsin. The requirements of the State's Radiation Protection Code were used as survey criteria. Radiation measurements of radium storage containers, radium capsule leakage tests, and monitoring of work surfaces for contamination were performed. Film badge monitoring data of whole body and extremity doses are presented for 221 individuals at 17 hospitals. Whole body doses during single treatments ranged from 10 to 1360 mrems per individual. The estimate of 500 mrems per treatment was determined as the dose aggregate to hospital personnel. Whole body doses from film badges are compared with analogous TLD doses. Four physicians and six technicians at nine hospitals participated in a study for monitoring the extremities with TLD. Cumulative extremity doses ranged from 28 to 6628 mrems per participant during the study. (U.S.)

The effects of age at time of exposure on the distribution and toxicity of radium 226 in the beagle dog

International Nuclear Information System (INIS)

Bruenger, F.W.; Lloyd, R.D.; Egger, M.J.

1989-01-01

The influence of age at time of injection of radium 226 on its skeletal deposition, retention and distribution, the pattern of bone tumour formation and the post-injection survival has been studied in beagles. Dogs received a single intravenous injection of radium 226 at an age of 3 months (juveniles), 17-19 months (young adults) or 60 months (mature), respectively. In spite of large differences in distribution and retention of the nuclide, the influence of age on bone tumour induction was moderate and the post-injection survivals were not significantly different, although a larger skeletal dose combined with a longer survival indicated a trend to a lower overall toxicity in the juvenile age group. (author)

Beryllium brazing considerations in CANDU fuel bundle manufacture

International Nuclear Information System (INIS)

Harmsen, J.; Pant, A.; Lewis, B.J.; Thompson, W.T.

2010-01-01

'Full text:' Appendages of CANDU fuel bundle elements are currently joined to zircaloy sheaths by vacuum beryllium brazing. Ongoing environmental and workplace concerns about beryllium combined with the continuous efforts by Cameco Fuel Manufacturing in its improvement process, initiated this study to find a substitute for pure beryllium. The presentation will review the necessary functionality of brazing alloy components and short list a series of alloys with the potential to duplicate the performance of pure beryllium. Modifications to current manufacturing processes based on in-plant testing will be discussed in relation to the use of these alloys. The presentation will conclude with a summary of the progress to date and further testing expected to be necessary.

Deuterium permeation and diffusion in high-purity beryllium

International Nuclear Information System (INIS)

Abramov, E.; Riehm, M.P.; Thompson, D.A.; Smeltzer, W.W.

1990-01-01

The permeation rate of deuterium through high-purity beryllium membranes was measured using the gas-driven permeation technique. The time-dependent and the steady-state deuterium flux data were analyzed and the effective diffusivities of the samples were determined. Using multilayer permeation theory the effects of surface oxide were eliminated and the diffusion coefficients of the bulk beryllium determined. The diffusion parameters obtained for the extra-grade beryllium samples (99.8%) are D 0 =6.7x10 -9 m 2 /s and E D =28.4 kJ/mol. For the high-grade beryllium samples (99%) the parameters are D 0 =8.0x10 -9 m 2 /s and E D =35.1 kJ/mol. (orig.)

Status of beryllium R and D in Japan

International Nuclear Information System (INIS)

Kawamura, H.; Ishida, K.

2004-01-01

Recently, several R and D program of beryllium for fusion are being promoted in Japan and community of beryllium study is growing up. In the R and D area of beryllium for solid breeding blanket, major subjects are beryllide application for prototype reactor, lifetime evaluation of neutron multiplier, impurity effect of beryllium and recycling of irradiated beryllium. Especially, the study of beryllide application has significant progress in these two years. The basic properties such as tritium inventory, oxidation behavior, steam interaction for stoichiometric Be 12 Ti fabricated by HIP (Hot Isostatic Pressing) have been studied and some advantages against beryllium were made clear. For manufacturing technology development, phase diagram and ductility improvement have been studied. And, Be 12 Ti pebbles with the improved microstructure were successfully fabricated by Rotating Electrode Process. In order to enhance the R and D activities, the R and D network consisted of industries, universities and laboratories in all Japan have been organized. Many collaboration and information exchange strongly promotes the R and D and some projects for commercial application have been launched form these activities. Also international collaborative project such as IEA and ISTC have been launched or planned. Recent result of R and D in Japan is described on this paper. (author)

Unusual case of radium exposure

International Nuclear Information System (INIS)

Toohey, R.E.; Sha, J.Y.; Urnezis, P.W.; Hwang, E.Y.

1984-01-01

We have determined the body content, distribution, retention, and excretion rate of 226 Ra for a uranium mill worker who inhaled 226 Ra in an unknown form. Radium was retained in the lung with a biological half-life of 120 days, an the amount initially inhaled was estimated to be 180 +- 30 Bq. These values, combined with an observed radon retention factor of 71%, implied a 50-year dose commitment of 0.16 +- 0.04 Sv to the lung. Although it is believed that this case represents an isolated incident, it is possible that some uranium mill workers may form a contemporary population that is occupationally exposed to radium. 5 references, 2 figures, 2 tables

Breast cancer in female radium dial workers first employed before 1930

International Nuclear Information System (INIS)

Adams, E.E.; Brues, A.M.

1980-01-01

Female radium dial workers first employed before 1930 were analyzed for breast cancer mortality and incidence using method and rate tables described by Monson and the Mantel-Haenszel summary chi-square test for significance. Of 1180 located women, 736 were measured to estimate radium intake. This measured group was analyzed for breast cancer mortality and incidence according to four possible risk factors: radium intake dose, duration of employment, age at first exposure, and parity. The measured women showed a significant excess of breast cancer incidence and mortality only among those women with a radium intake of 50 μCi or greater

Quantitative method of determining beryllium or a compound thereof in a sample

Science.gov (United States)

McCleskey, T. Mark; Ehler, Deborah S.; John, Kevin D.; Burrell, Anthony K.; Collis, Gavin E.; Minogue, Edel M.; Warner, Benjamin P.

2010-08-24

A method of determining beryllium or a beryllium compound thereof in a sample, includes providing a sample suspected of comprising beryllium or a compound thereof, extracting beryllium or a compound thereof from the sample by dissolving in a solution, adding a fluorescent indicator to the solution to thereby bind any beryllium or a compound thereof to the fluorescent indicator, and determining the presence or amount of any beryllium or a compound thereof in the sample by measuring fluorescence.

Bioenvironmental Engineering Guide to Beryllium

Science.gov (United States)

2017-07-26

Dermal contact with beryllium can result in dermatitis resembling first- or second-degree burns and skin granulomas [7]. Beryllium dust, fume...minute short-term exposure limit (STEL) of 2.0 µg/m3 [§1910.1024(c)(2) & §1926.1124(c)(2)], and added provisions to prevent skin contact [§1910.1024(b...document you want more information, contact the Environmental, Safety, and Occupational Health (ESOH) Service Center at DSN 798-3764, 1-888-232-ESOH (3764

Preparation of a sinterable beryllium oxide through decomposition of beryllium hydroxide (1963); Preparation d'un oxyde de beryllium frittable par decomposition de l'hydiloxyde (1963)

Energy Technology Data Exchange (ETDEWEB)

Bernier, M [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1963-07-01

In the course of the present study, we have attempted to precise the factors which among the ones effective in the course of the preparation of the beryllium hydroxide and oxide and during the sintering have an influence on the final result: the density and homogeneity of the sintered body. Of the several varieties of hydroxides precipitated from a sulfate solution the {beta}-hydroxide only is always contaminated with beryllium sulfate and cannot be purified even by thorough washing. We noticed that those varieties of the hydroxide (gel, {alpha}, {beta}) have different decomposition rates; this behaviour is used to identify and even to dose the different species in ({alpha}, {beta}) mixtures. The various hydroxides transmit to the resulting oxides the shape they had when precipitated. Accordingly the history of the oxide is revealed by its behaviour during its fabrication and sintering. By comparing the results of the sintering operation with the various measurements performed on the oxide powders we are led to the conclusion that an oxide obtained from beryllium hydroxide is sinterable under vacuum if the following conditions are fulfilled: the particle size must lie between 0.1 and 0.2 {mu} and the BeSO{sub 4} content of the powder must be less than 0.25 per cent wt (expressed as SO{sub 3}/BeO). The best fitting is obtained with the oxide issued from an {alpha}-hydroxide precipitated as very small aggregates and with a low sulfur-content. We have observed that this is also the case for the oxide obtained by direct calcination of beryllium sulfate. (author) [French] Au cours de cette etude, nous avons cherche a preciser les facteurs qui, intervenant tout au long de la preparation de l'hydroxyde, puis de l'oxyde de beryllium et enfin du frittage, peuvent avoir une influence sur le resultat final: la densite et l'homogeneite du fritte. Parmi tous les hydroxydes precipites d'une solution de sulfate, seul l'hydroxyde {beta} est toujours fortement pollue par le sulfate

Impurities effect on the swelling of neutron irradiated beryllium

International Nuclear Information System (INIS)

Donne, M.D.; Scaffidi-Argentina, F.

1995-01-01

An important factor controlling the swelling behaviour of fast neutron irradiated beryllium is the impurity content which can strongly affect both the surface tension and the creep strength of this material. Being the volume swelling of the old beryllium (early sixties) systematically higher than that of the more modem one (end of the seventies), a sensitivity analysis with the aid of the computer code ANFIBE (ANalysis of Fusion Irradiated BEryllium) to investigate the effect of these material properties on the swelling behaviour of neutron irradiated beryllium has been performed. Two sets of experimental data have been selected: the first one named Western refers to quite recently produced Western beryllium, whilst the second one, named Russian refers to relatively old (early sixties) Russian beryllium containing a higher impurity rate than the Western one. The results obtained with the ANFIBE Code were assessed by comparison with experimental data and the used material properties were compared with the data available in the literature. Good agreement between calculated and measured values has been found

Study on neutron irradiation behavior of beryllium as neutron multiplier

Energy Technology Data Exchange (ETDEWEB)

Ishitsuka, Etsuo [Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment

1998-03-01

More than 300 tons beryllium is expected to be used as a neutron multiplier in ITER, and study on the neutron irradiation behavior of beryllium as the neutron multiplier with Japan Materials Testing Reactor (JMTR) were performed to get the engineering data for fusion blanket design. This study started as the study on the tritium behavior in beryllium neutron reflector in order to make clear the generation mechanism on tritium of JMTR primary coolant since 1985. These experiences were handed over to beryllium studies for fusion study, and overall studies such as production technology of beryllium pebbles, irradiation behavior evaluation and reprocessing technology have been started since 1990. In this presentation, study on the neutron irradiation behavior of beryllium as the neutron multiplier with JMTR was reviewed from the point of tritium release, thermal properties, mechanical properties and reprocessing technology. (author)

Modeling of hydrogen interactions with beryllium

Energy Technology Data Exchange (ETDEWEB)

Longhurst, G.R. [Lockheed Martin Idaho Technologies Co., Idaho Falls, ID (United States)

1998-01-01

In this paper, improved mathematical models are developed for hydrogen interactions with beryllium. This includes the saturation effect observed for high-flux implantation of ions from plasmas and retention of tritium produced from neutronic transmutations in beryllium. Use of the models developed is justified by showing how they can replicated experimental data using the TMAP4 tritium transport code. (author)

THE IDAHO NATIONAL LABORATORY BERYLLIUM TECHNOLOGY UPDATE

International Nuclear Information System (INIS)

Glen R. Longhurst

2007-01-01

A Beryllium Technology Update meeting was held at the Idaho National Laboratory on July 18, 2007. Participants came from the U.S., Japan, and Russia. There were two main objectives of this meeting. One was a discussion of current technologies for beryllium in fission reactors, particularly the Advanced Test Reactor and the Japan Materials Test Reactor, and prospects for material availability in the coming years. The second objective of the meeting was a discussion of a project of the International Science and Technology Center regarding treatment of irradiated beryllium for disposal. This paper highlights discussions held during that meeting and major conclusions reached

Deuterium permeation and diffusion in high purity beryllium

International Nuclear Information System (INIS)

Abramov, E.

1990-05-01

The permeation rate of deuterium through high-purity beryllium membranes was measured using the gas-driven permeation technique. The time-dependent and the steady-state deuterium flux data were analyzed and the effective diffusivities of the samples were determined. A multilayer permeation theory was used in order to eliminate the surface oxide effects and the diffusion coefficients of the bulk beryllium were determined. The diffusion parameters obtained for the extra-grade beryllium samples (99.8%) are D 0 = 6.7 x 10 -9 [m 2 /s] and E D = 28.4 [KJ/mol]; and for the high-grade beryllium samples (99%) the parameters are D 0 = 8.0 x 10 -9 [m 2 /s] and E D = 35.1 [KJ/mol

Conditioning radium needles for long term storage : Sri Lankan experience

International Nuclear Information System (INIS)

Ranjith, H.L.A.; Shantha, T.H.S.; Gunaratne, M.G.J.; De Silva, U.W.K.H.; Perera, H.P.H.

2000-01-01

Radium the first radioisotope invented by Madame Curie was used for cancer therapy for the intracavitory treatment of cervical cancers and as oral implants etc. Radium needles and other geometries were made in standard strengths and Radium therapy enjoyed a heyday during the 1st half of the 20th century. Radium-226 is a long-lived radioactive material with a half-life of 1600 years. The use of radium was abandoned in the world in 1980s with the invention of short lived radioactive materials offering remote after loading systems which minimise radiation protection and waste disposal problems associated with long lived radioactive materials. This paper reports the conditioning procedure of the spent radium sources for long term storage (less than 20 years) and transport to national/ international stores if needed. The dose received by those involved in this exercise is also discussed in terms of radiation protection. The Ra was contained for long term storage according to international radiation safety regulations with a surface dose of less than 2 mSv per hour in a conditioned package having 17.5 GBq activity and can be transported to national/international stores if needed. The highest dose received during the exercise is well within the recommended dose limits for occupational exposures (20 and 500 mSv per year) for whole body and extremities respectively

Dosimetry of head carcinomas in radium cases

International Nuclear Information System (INIS)

Schlenker, R.A.; Harris, M.J.

1979-01-01

Dose rate calculations, combined with observations of tissue dimensions, lead to the conclusion that radon and its daughters in the airspace produce a greater dose rate in the mastoid air cell epithelium, the tissue at risk for mastoid carcinomas in radium cases, than do radium and its daughters in bone. As the conclusion is based on limited tissue data, assumed values for the radioactivity in bone and airspace, and a number of important assumptions, it must be considered tentative

Formation of cellular structure in beryllium at plastic working

International Nuclear Information System (INIS)

Papirov, I.I.; Nikolaenko, A.A.; Shokurov, V.S.; Pikalov, A.I.

2013-01-01

Conditions of cellular structure formation are investigated at various kinds of deformation and heat treatment of beryllium ingots. It is shown that the cellular structure plays the important role in formation of complex of physical mechanical properties of beryllium. Influence of impurity, various conditions of deformation (temperature, squeezing degree) and heat treatments on substructure, texture and mechanical properties of metal is investigated. Optimum conditions of rolling and heat treatments of beryllium are defined. The way of sign-variable cyclic deformation of beryllium ingots is offered for reception quasi-isotropic fine-grained metal. Physical-mechanical properties of ultra fine-grained metal are studied

Determination of radium 226 and 228 in water

International Nuclear Information System (INIS)

Jeanmaire, L.; Willemot, J.M.; Verry, M.

1989-01-01

Usually, only radium 226 is measured in water since determination of radium 228 is not easy at the natural levels. A technique has therefore been developed to measure, at the same time and at low radioactivity levels, two radionuclides most often associated in water and with similar toxicity. Computer data processing brings significant improvements though calculation can be manually done [fr

Track detection methods of radium measurements

International Nuclear Information System (INIS)

Somogyi, G.

1986-06-01

The principles of tack formation and processing including the description of etching and etch-track evaluation for the preferably used plastic track detectors are discussed. Measuring methods to determine 226 Ra activity based either on the mapping of alpha-decaying elements in the complete U-Ra series by alpha-radiography, or on the measurement of uranium alone by neutron induced fissionography, or on the alpha-decay measurement of 222 Rn, the first daughter element of radium, and finally on the measurement of alpha-tracks originating from radium itself, which is separated from its parent nuclides are described in detail. (V.N.)

Some scientific landmarks of the MIT radium toxicity studies

International Nuclear Information System (INIS)

Maletskos, C.J.

1996-01-01

Until the recent forced termination of the studies on radium toxicity, more than six decades of investigation and research have been devoted to them. These studies involve ∼2400 subjects who were exposed to long-term internally deposited radium [high linear energy transfer (LET)], whose health status was evaluated in great detail and whose radiation dosimetry was based on measurements of their actual radium body burdens. The quality and usefulness of these studies are, therefore, in sharp contrast to other human radiation-exposure studies that involve instantaneous or somewhat protracted external low-LET exposures and inferred radiation dose, as in the atomic-bomb survivor studies. As a consequence of national news in 1932 concerning the gruesome death of a prominent Pittsburgh businessman and sportsman, Robley D. Evans became involved with radium toxicity, and its study became an important project when he joined the faculty of the Massachusetts Institute of Technology physics department and set up the interdisciplinary Radioactivity Center

Preparation of copper-beryllium alloys from Indian beryl

International Nuclear Information System (INIS)

Paul, C.M.; Sharma, B.P.; Subba Rao, K.S.; Rajadhyaksha, M.G.; Sundaram, C.V.

1975-01-01

The paper presents the results of laboratory-scale investigations on the preparation of copper-beryllium and aluminium beryllium master alloys starting from Indian beryl and adopting the fluoride process. The flowsheet involves: (1) conversion of the Be-values in beryl into water soluble sodium beryllium fluoride, (2) preparation of beryllium hydroxide by alkali treatment of aqueous Na 2 BeF 4 (3) conversion of Be(OH) 2 to (NH 4 ) 2 BeF 4 by treatment with NH 4 HF 2 (4) thermal decomposition of (NH 4 ) 2 BeF 4 to BeF 2 and (5) magnesium reduction of BeF 2 (without/with) the addition of copper/aluminium to obtain beryllium metal/alloys. The method has been successfully employed for the preparation of Cu-Be master alloys containing about 8% Be and free of Mg on a 200 gm scale. A1-80% Be master alloys have also been prepared by this method. Toxicity and health hazards associated with Be are discussed and the steps taken to ensure safe handling of Be are described. (author)

10 CFR 850.20 - Baseline beryllium inventory.

Science.gov (United States)

2010-01-01

... 10 Energy 4 2010-01-01 2010-01-01 false Baseline beryllium inventory. 850.20 Section 850.20 Energy... Baseline beryllium inventory. (a) The responsible employer must develop a baseline inventory of the... inventory, the responsible employer must: (1) Review current and historical records; (2) Interview workers...

Characterization of shocked beryllium

Directory of Open Access Journals (Sweden)

Papin P.A.

2012-08-01

Full Text Available While numerous studies have investigated the low-strain-rate constitutive response of beryllium, the combined influence of high strain rate and temperature on the mechanical behavior and microstructure of beryllium has received limited attention over the last 40 years. In the current work, high strain rate tests were conducted using both explosive drive and a gas gun to accelerate the material. Prior studies have focused on tensile loading behavior, or limited conditions of dynamic strain rate and/or temperature. Two constitutive strength (plasticity models, the Preston-Tonks-Wallace (PTW and Mechanical Threshold Stress (MTS models, were calibrated using common quasi-static and Hopkinson bar data. However, simulations with the two models give noticeably different results when compared with the measured experimental wave profiles. The experimental results indicate that, even if fractured by the initial shock loading, the Be remains sufficiently intact to support a shear stress following partial release and subsequent shock re-loading. Additional “arrested” drive shots were designed and tested to minimize the reflected tensile pulse in the sample. These tests were done to both validate the model and to put large shock induced compressive loads into the beryllium sample.

SAFARI-1 research reactor beryllium reflector element replacement, management and relocation

International Nuclear Information System (INIS)

Kock, Marisa De; Vlok, Jwh; Steynberg, B.J.

2012-01-01

The beryllium (Be) reflector elements of the SAFARI-1 Research Reactor were replaced in October 2011 as part of the Ageing Management Programme of the reactor. After more than three million MWh of operation over a period of 47 years, core reloading became more difficult due to the geometric deformation of the beryllium reflector elements. During the replacement of the reflector elements, criticality and reactivity worth experiments were performed and found to compare favorably with calculated values. A Beryllium Management Programme was established at SAFARI-1 to identify and apply effective and appropriate actions and practices for managing the ageing of the new beryllium reflector elements. This will provide timely detection and mitigation of ageing mechanisms relevant to beryllium reflector elements, supporting the life extension of these elements. These actions and practices include monitoring of the tritium levels in the primary water, calculating and measuring the fluxes within the beryllium reflector positions, measuring the straightness of the elements to track geometric deformation and visually inspecting the reflector elements for crack formation. Acceptance criteria indicating the end of life of the elements were established. These criteria take into account the smallest gap that could exist between elements, sudden changes in the tritium levels and formation of cracks. All the data obtained through the Beryllium Management Programme are recorded in a database. Additional benefits gained through a Beryllium Management Programme are the availability of a complete irradiation history of the beryllium reflector elements at any point in time and the establishment of a knowledge base to assists in the understanding of the behavior of the beryllium reflector elements in an irradiation environment. Straightness baseline measurements of the new beryllium reflector elements were performed with a beryllium straightness measurement tool, designed at SAFARI-1. The

SAFARI-1 research reactor beryllium reflector element replacement, management and relocation

Energy Technology Data Exchange (ETDEWEB)

Kock, Marisa De; Vlok, Jwh; Steynberg, B J [South Africa Atomic Energy Corporation (Necsa) (South Africa)

2012-03-15

The beryllium (Be) reflector elements of the SAFARI-1 Research Reactor were replaced in October 2011 as part of the Ageing Management Programme of the reactor. After more than three million MWh of operation over a period of 47 years, core reloading became more difficult due to the geometric deformation of the beryllium reflector elements. During the replacement of the reflector elements, criticality and reactivity worth experiments were performed and found to compare favorably with calculated values. A Beryllium Management Programme was established at SAFARI-1 to identify and apply effective and appropriate actions and practices for managing the ageing of the new beryllium reflector elements. This will provide timely detection and mitigation of ageing mechanisms relevant to beryllium reflector elements, supporting the life extension of these elements. These actions and practices include monitoring of the tritium levels in the primary water, calculating and measuring the fluxes within the beryllium reflector positions, measuring the straightness of the elements to track geometric deformation and visually inspecting the reflector elements for crack formation. Acceptance criteria indicating the end of life of the elements were established. These criteria take into account the smallest gap that could exist between elements, sudden changes in the tritium levels and formation of cracks. All the data obtained through the Beryllium Management Programme are recorded in a database. Additional benefits gained through a Beryllium Management Programme are the availability of a complete irradiation history of the beryllium reflector elements at any point in time and the establishment of a knowledge base to assists in the understanding of the behavior of the beryllium reflector elements in an irradiation environment. Straightness baseline measurements of the new beryllium reflector elements were performed with a beryllium straightness measurement tool, designed at SAFARI-1. The

Occupational and non-occupational allergic contact dermatitis from beryllium

Energy Technology Data Exchange (ETDEWEB)

Vilaplana, J; Romaguera, C; Grimalt, F [Allergy Department, Dermatological Service Hospital Clinico, Barcelona (Spain)

1992-01-01

There are various references to sensitization to beryllium in the literature. Since introducing a patch testing series for patients with suspected sensitization to metals, we have found 3 cases of sensitization to beryllium. Of these 3 cases, we regard the first 2 as having relevant sensitization. Beryllium chloride (1% pet.) was positive in 3 patients and negative in 150 controls. (au).

Occupational and non-occupational allergic contact dermatitis from beryllium

International Nuclear Information System (INIS)

Vilaplana, J.; Romaguera, C.; Grimalt, F.

1992-01-01

There are various references to sensitization to beryllium in the literature. Since introducing a patch testing series for patients with suspected sensitization to metals, we have found 3 cases of sensitization to beryllium. Of these 3 cases, we regard the first 2 as having relevant sensitization. Beryllium chloride (1% pet.) was positive in 3 patients and negative in 150 controls. (au)

Radium 226 and uranium isotopes simultaneously determination in water samples using liquid scintillation counter

International Nuclear Information System (INIS)

Al-Masri, M.S.; Al-Akel, B.; Saaid, S.; Nashawati, A.

2007-04-01

In this work a method has been developed to determine simultaneously Radium 226 and Uranium isotopes in water samples by low back ground Liquid Scintillation Counter. Radium 226 was determined by its progeny Polonium 214 after one month of sample storage in order to achieve the equilibrium between Radium 226 and Polonium 214. Uranium isotopes were determined by subtracting Radium 226 activity from total alpha activity. The method detection limits were 0.049 Bq/L and 0.176 Bq/L for Radium 226 and Uranium isotopes respectively. The repeatability limits were ± 0.32 Bq/L and ± 0.9 Bq/L for Radium 226 and Uranium isotopes respectively. While relative errors were % 9.5 and %18.2 for Radium 226 and Uranium isotopes respectively. On the other hand, the report presented the results of different standard and natural samples.(author)

The structure, properties and performance of plasma-sprayed beryllium for fusion applications

International Nuclear Information System (INIS)

Castro, R.G.; Stanek, P.W.; Elliott, K.E.

1995-01-01

Plasma-spray technology is under investigation as a method for producing high thermal conductivity beryllium coatings for use in magnetic fusion applications. Recent investigations have focused on optimizing the plasma-spray process for depositing beryllium coatings on damaged beryllium surfaces. Of particular interest has been optimizing the processing parameters to maximize the through-thickness thermal conductivity of the beryllium coatings. Experimental results will be reported on the use of secondary H 2 gas additions to improve the melting of the beryllium powder and transferred-arc cleaning to improve the bonding between the beryllium coatings and the underlying surface. Information will also be presented on thermal fatigue tests which were done on beryllium coated ISX-B beryllium limiter tiles using 10 sec cycle times with 60 sec cooldowns and an International Thermonuclear Experimental Reactor (ITER) relevant divertor heat flux slightly in excess of 5 MW/m 2

Radon generator and the method of radium carrier fabrication

International Nuclear Information System (INIS)

Czerski, B.

1992-01-01

The radon generator construction and the method of radium carrier fabrication has been the subject of the patent. The generator is a cylindrical vessel with gas valves system and two filters inside. Between them the radium carrier has been located. As a carrier polyurethane foam has been used. The carrier is obtained in a generator vessel from polyester resin in the presence of activated mixture of engine oil, zinc-organic catalyst and toluene. To the obtained mixture the radium chloride in the solution of hydrochloric acid is added. The carrier foam is produced by mechanical stirring of substrates inside the vessel and drying in 50 C in a heater. 1 fig

Deuterium/hydrogen isotope exchange on beryllium and beryllium nitride; Deuterium/Wasserstoff-Isotopenaustausch an Beryllium und Berylliumnitrid

Energy Technology Data Exchange (ETDEWEB)

Dollase, Petra; Eichler, Michael; Koeppen, Martin; Dittmar, Timo; Linsmeier, Christian [Forschungszentrum Juelich GmbH, Institut fuer Energie- und Klimaforschung - Plasmaphysik (Germany)

2016-07-01

In the fusion experiments JET and ITER, the first wall is made up of beryllium. The use of nitrogen is discussed for radiative cooling in the divertor. This can react with the surface of the first wall to form beryllium nitride (Be{sub 3}N{sub 2}). The hydrogen isotopes deuterium and tritium, which react in the fusion reaction to helium and a neutron, are used as fuel. Since the magnetic confinement of the plasma is not perfect, deuterium and tritium ions are also found on the beryllium wall and can accumulate there. This should be avoided due to the radioactivity of tritium. Therefore the isotope exchange with deuterium is investigated to regenerate the first wall. We investigate the isotopic exchange of deuterium and protium in order to have not to work with radioactive tritium. The ion bombardment is simulated with an ion source. With voltages up to a maximum of 5 kV, deuterium and protic hydrogen ions are implanted in polycrystalline Be and Be{sub 3}N{sub 2}. The samples are then analyzed in situ using X-ray photoelectron spectroscopy (XPS) and thermal desorption spectroscopy (TDS). Subsequently, samples prepared under the same conditions are characterized ex-situ by means of nuclear reaction analysis (NRA). [German] In den Fusionsexperimenten JET und ITER besteht die erste Wand im Hauptraum aus Beryllium (Be). Zur Strahlungskuehlung im Divertor wird der Einsatz von Stickstoff diskutiert. Dieser kann mit der Oberflaeche der ersten Wand zu Berylliumnitrid (Be{sub 3}N{sub 2}) reagieren. Als Brennstoff werden die Wasserstoffisotope Deuterium und Tritium eingesetzt, die in der Fusionsreaktion zu Helium und einem Neutron reagieren. Da der magnetische Einschluss des Plasmas nicht perfekt ist, treffen auch Deuterium- und Tritiumionen auf die Berylliumwand auf und koennen sich dort anreichern. Das soll aufgrund der Radioaktivitaet von Tritium unbedingt vermieden werden. Daher wird zur Regenerierung der ersten Wand der Isotopenaustausch mit Deuterium untersucht. Wir

The Rocky Flats Environmental Technology Site beryllium characterization project

International Nuclear Information System (INIS)

Morrell, D.M.; Miller, J.R.; Allen, D.F.

1999-01-01

A site beryllium characterization project was completed at the Rocky Flats Environmental Technology Site (RFETS) in 1997. Information from historical reviews, previous sampling surveys, and a new sampling survey were used to establish a more comprehensive understanding of the locations and levels of beryllium contamination in 35 buildings. A feature of the sampling strategy was to test if process knowledge was a good predictor of where beryllium contamination could be found. Results revealed that this technique was effective at identifying where surface contamination levels might exceed the RFETS smear control level but that it was not effective in identifying where low concentrations of beryllium might be found

Phosphorus-containing azo compounds as analytical reagents for beryllium

International Nuclear Information System (INIS)

Lisenko, N.F.; Dolzhnikova, E.N.; Petrova, G.S.; Tsvetkov, E.N.; Vsesoyuznyj Nauchno-Issledovatel'skij Inst. Khimicheskikh Reaktivov i Osobo Chistykh Veshchestv, Moscow; AN SSSR, Moscow. Inst. Ehlementoorganicheskikh Soedinenij)

1979-01-01

The interaction of beryllium with six new azocompounds based on chromotropic or R-acids and o-aminophenyl-phenylphosphonic acids is studied. A sharp difference in the detection limit for beryllium by the two groups of compounds is found. Azoderivatives based on chromotropic acid are promising agent for beryllium due to sufficiently high selectivity. The introduction of the methyl-group into the o-position of the phosphorus-containing group improves the analytical properties of agents. Techniques are developed for the determination of beryllium in bronze, sewage water and in an artificial mixture using a sodium salt of 1.8-dioxi-2 [2' - (oxi- (o-methylphenyl)-phosphenyl)-phenilazo]-naphtalene-3.6-disulfoacid

The environmental behaviour of radium. V.2

International Nuclear Information System (INIS)

1990-01-01

The objective of this publication is to provide an up to date review of the environmental behaviour of radium, including methods for analysis, assessment and control. The need for a reference text on the subject was identified at an early stage of the International Atomic Energy Agency's Co-ordinated Research Programme (CRP) on radium behaviour in relation to uranium mining and milling wastes. This publication deals with the sources, properties, environmental behaviour and the methods of analysis, control and assessment of 226 Ra. It is an outgrowth of Agency programmes directed towards the environmental problems involved in uranium mining and milling. The emphasis in several of the sections reflects these origins. For example, many of the contributions in Volume 2 of this report on technologically enhanced sources of radium (Part 1), methods of control and abatement (Part 2) and the impact on man (Part 3) are concerned with uranium mining and milling. Refs, figs and tabs

Influence of physicochemical properties of beryllium particles on cultured cell toxicity

International Nuclear Information System (INIS)

Finch, G.L.; Brooks, A.L.; Hoover, M.D.; Cuddihy, R.G.

1988-01-01

The toxicity of beryllium oxide (BeO)), beryllium metal, and beryllium sulfate (BeSO 4 ) was studied in two cell lines, Chinese hamster ovary cells (CHO) and lung epithelial cells (LEC). Beryllium oxide particles were prepared at either 500 or 1000 deg. C, and two different particle sizes of beryllium metal were used. Following a 20-h exposure to beryllium compounds, cells were grown in culture to quantitate cloning ability relative to controls as a measure of cell killing, The LEC cultures were more sensitive to beryllium cytotoxicity than the CHO cells. When expressed on the basis of the mass of material added to the cultures, the order of toxicity was BeSO 4 ≥ 500 deg. C -BeO > 1000 deg. C -BeO > Be metal (small) Be metal (large). When cytotoxic effects were expressed on the basis of particulate surface rather than mass, the relative differences in toxicity between compounds was decreased. The order of toxicity was Be metal (small) ∼ Be metal (large) ∼ 500 deg. C-BeO ∼ 1000 deg. C-BeO. These data indicate that solubility influences beryllium toxicity to short-term cell cultures. (author)

Long-term retention of radium in female former dial workers

International Nuclear Information System (INIS)

Rundo, J.; Keane, A.T.; Essling, M.A.

1984-01-01

The results of measurements of radium contents in 13 women made over 20 years or more were used to measure radium retention. The women were all employed at different studios of the same Illinois plant as luminous dial workers for up to 4 years. The data for each woman were fitted to an exponential function of time, yielding a biological half-life of approximately 30 to 60 years. There was a strong negative correlation between elimination rate and body content, suggesting an effect of radiation of bone resorption or remodelling. A strong negative correlation was observed between the elimination rate and the reduced x-ray score, a measure of bone damage observed radiographically in the same subjects. Age at first exposure and duration of exposure were not significantly correlated with the elimination rate. The concentration of radium in soft tissues from eight other subjects, expressed as a percentage of the terminal radium content, decreased with increasing body content, providing further evidence that radiation was affecting the elimination rate. An effect of radiation on the late retention of radium has been demonstrated. 10 references, 4 figures, 2 tables

Leaching of radium from mine deposits - application for planning of ground reclamation

International Nuclear Information System (INIS)

Chalupnik, S.

2002-01-01

Saline waters occurring in underground coal mines in Poland often contain natural radioactive isotopes, mainly 226 Ra from uranium series and 228 Ra from thorium series. Approximately 40% of total amount of radium remains underground in a form of radioactive deposits, but 225 MBq of 226 Ra and 400 MBq of 228 Ra are released daily into the rivers with mine effluents through surface settling ponds. Very peculiar situation is observed in coal mines, where as a result of precipitation of radium from radium-bearing waters radioactive deposits are formed. Sometimes natural radioactivity of such materials is very high, in case of scaling from coal mines radium concentration may reach 400000 Bq/kg - similar activity as for 3% uranium ore. Usually such deposits can be found underground, but sometimes co-precipitation of radium and barium takes place on the surface, in settling pond and in rivers. Therefore maintenance of solid and liquid waste with technologically enhanced natural radioactivity (TENORM) is a very important subject. Lately another problem appeared - due to the decrease of the production in Poland coal industry and dismantling of several coal mines, also the ground reclamation should be done in their vicinity. But in several cases deposits in the ponds contain enhanced levels of radium concentration. Therefore laboratory tests were done to investigate a possibility of the re-entry of radium into ground water or river waters from such deposits. Results show, that in the case of insoluble barium and radium sulphates co-precipitated out from waters type A, re-entry ratio is very small. Different situation can be observed in case of radium, adsorbed on bottom of sediments from waters type B, because re-entry ratio is much higher. Nevertheless, this phenomenon seems to be not so important and significant for the further pollution of the adjacent areas of the settling ponds in the future. (author)

Beryllium and zirconium

International Nuclear Information System (INIS)

Salesse, Marc

1959-01-01

Pure beryllium and zirconium, both isolated at about the same date but more than a century ago remained practically unused for eighty years. Fifteen years ago they were released from this state of inactivity by atomic energy, which made them into current metal a with an annual production which runs into tens of tons for the one and thousands for the other. The reasons for this promotion promise well for the future of the two metals, which moreover will probably find additional uses in other branches of industry. The attraction of beryllium and zirconium for atomic energy is easily explained. The curve of figure 1 gives the price per gram of uranium-235 as a function of enrichment: this price increases by about a factor of 3 on passing from natural uranium (0, 7 percent 235 U) to almost pure uranium-235. Because of their tow capture cross-section beryllium and zirconium make it possible, or at least easier, to use natural uranium and they thus enjoy an advantage the extent of which must be calculated for each reactor or fuel element project, but which is generally considerable. It will be seen later that this advantage should be based on figures which are even more favourable that would appear from the simple ratio 3 of the price of pure uranium- 235 contained in natural uranium. Reprint of a paper published in 'Industries Atomiques' - n. 1-2, 1959

Inspection of radium-needles

International Nuclear Information System (INIS)

Stekelenburg, L.H.M. van.

1976-01-01

A method for leak testing of a radium point source is given. The point source was placed for three days in a closed bottle containing 15 ml of scintillation liquid (Instagel). After removing the point source, the decrease in activity was measured over a 25 day period

Dose-response relationships for female radium dial workers: A new look

International Nuclear Information System (INIS)

Rowland, R.E.

1994-01-01

The values of initial systemic intake and of skeletal dose for all of the U.S. radium cases have recently been revised. This revision was required following the demonstrations by Rundo and by Keane that humans who were exposed to radium as adults lost radium at a rate that depended on the quantity of radium originally deposited within their bodies. These new values have been used to define new dose-response relationships for both the bone sarcomas and the carcinomas arising in the paranasal sinuses and mastoid air cells induced by internally deposited radium. The population examined was employed in the U.S. dial painting industry prior to 1950 and consisted of 1530 female dial workers for whom radium body burden measurements were available. By the end of 1990, 46 cases of bone sarcomas and 19 cases of head carcinomas had been diagnosed in this cohort. The head carcinoma incidence can be adequately fitted by a simple linear function, as was found in previous analyses. The bone sarcoma cases were previously fitted by a dose-squared-exponential function. With the revised values of systemic intake, the sarcoma results could not be satisfactorily fitted with this expression. When the exponent on D was increased to larger values, excellent fits were obtained

Removal of Radium isotopes from oil co-produced water using Bentonite

International Nuclear Information System (INIS)

Al Masri, M.S.; Al Attar, L.; Budeir, Y.; Al Chayah, O.

2010-01-01

In view of environmental concern, sorption of radium on natural bentonite mineral (Aleppo, Syria) was investigated using batch-type method. Data were expressed in terms of distribution coefficients. An attempt to increase the selectivity of bentonite for radium was made by preparing M-derivatives. Loss of mineral crystallinity in acidic media and the formation of new phase, such as BaCO 3 , in Ba-derivative were imposed by XRD characterisations. Of the cationic forms, Na-bentonite had shown the highest affinity. Mechanisms of radium uptake were pictured using M-derivatives and simulated radium solutions. The obtained results indicated that surface sorption/surface ion exchange were the predominated processes. The distinct sorption behaviour observed with Ba-form was, possibly, a reflection of radium co-precipitation with barium carbonate. The competing order of macro component, likely present in waste streams, was drawn by studying different concentrations of the corresponding salt media. As an outcome, sodium was the weakest inhibitor. The performance of natural bentonite and the most selective forms, i.e. Ba- and Na-derivatives, to sorb radium from actual oil co-produced waters, collected form Der Ezzor Petroleum Company (DEZPC), was studied. This mirrored the influential effect of waters pH over other comparable parameters. (author)

Validation of cleaning method for various parts fabricated at a Beryllium facility

Energy Technology Data Exchange (ETDEWEB)

Davis, Cynthia M. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2015-12-15

This study evaluated and documented a cleaning process that is used to clean parts that are fabricated at a beryllium facility at Los Alamos National Laboratory. The purpose of evaluating this cleaning process was to validate and approve it for future use to assure beryllium surface levels are below the Department of Energy’s release limits without the need to sample all parts leaving the facility. Inhaling or coming in contact with beryllium can cause an immune response that can result in an individual becoming sensitized to beryllium, which can then lead to a disease of the lungs called chronic beryllium disease, and possibly lung cancer. Thirty aluminum and thirty stainless steel parts were fabricated on a lathe in the beryllium facility, as well as thirty-two beryllium parts, for the purpose of testing a parts cleaning method that involved the use of ultrasonic cleaners. A cleaning method was created, documented, validated, and approved, to reduce beryllium contamination.

Extraction of beryllium sulfate by a long chain amine; Extraction du sulfate de beryllium par une amine a longue chaine

Energy Technology Data Exchange (ETDEWEB)

Etaix, E.S. [Commissariat a l' Energie Atomique, Fontenay-Aux-Roses (France). Centre d' Etudes Nucleaires

1968-06-01

The extraction of sulfuric acid in aqueous solution by a primary amine in benzene solution, 3-9 (diethyl) - 6-amino tri-decane (D.E.T. ) - i.e., with American nomenclature 1-3 (ethyl-pentyl) - 4-ethyl-octyl amine (E.P.O.) - has made it possible to calculate the formation constants of alkyl-ammonium sulfate and acid sulfate. The formula of the beryllium and alkyl-ammonium sulfate complex formed in benzene has next been determined, for various initial acidity of the aqueous solution. Lastly, evidence has been given of negatively charged complexes of beryllium and sulfate in aqueous solution, through the dependence of the aqueous sulfate ions concentration upon beryllium extraction. The formation constant of these anionic complexes has been evaluated. (author) [French] L'etude de l'extraction de l'acide sulfurique en solution aqueuse par une amine primaire en solution dans le benzene, le diethyl-3,9 amino-6 tridecane (D.E.T.) - autre nom americain 1-3 (ethylpentyl) - 4-ethyloctylamine (E.P.O.) a permis de calculer les constantes de formation du sulfate et de l'hydrogenosulfate d'alkyl-ammonium. La formule du complexe de sulfate de beryllium et d'alkyl-ammonium forme en solution benzenique a ete ensuite determinee pour diverses acidites initiales de la solution aqueuse. Enfin, l'influence de la concentration des ions sulfate de la phase aqueuse sur l'extraction du beryllium a mis en evidence la formation en solution aqueuse de complexes anioniques de sulfate et de beryllium dont la constante de formation a ete evaluee. (auteur)

Extraction of beryllium sulfate by a long chain amine; Extraction du sulfate de beryllium par une amine a longue chaine

Energy Technology Data Exchange (ETDEWEB)

Etaix, E S [Commissariat a l' Energie Atomique, Fontenay-Aux-Roses (France). Centre d' Etudes Nucleaires

1968-06-01

The extraction of sulfuric acid in aqueous solution by a primary amine in benzene solution, 3-9 (diethyl) - 6-amino tri-decane (D.E.T. ) - i.e., with American nomenclature 1-3 (ethyl-pentyl) - 4-ethyl-octyl amine (E.P.O.) - has made it possible to calculate the formation constants of alkyl-ammonium sulfate and acid sulfate. The formula of the beryllium and alkyl-ammonium sulfate complex formed in benzene has next been determined, for various initial acidity of the aqueous solution. Lastly, evidence has been given of negatively charged complexes of beryllium and sulfate in aqueous solution, through the dependence of the aqueous sulfate ions concentration upon beryllium extraction. The formation constant of these anionic complexes has been evaluated. (author) [French] L'etude de l'extraction de l'acide sulfurique en solution aqueuse par une amine primaire en solution dans le benzene, le diethyl-3,9 amino-6 tridecane (D.E.T.) - autre nom americain 1-3 (ethylpentyl) - 4-ethyloctylamine (E.P.O.) a permis de calculer les constantes de formation du sulfate et de l'hydrogenosulfate d'alkyl-ammonium. La formule du complexe de sulfate de beryllium et d'alkyl-ammonium forme en solution benzenique a ete ensuite determinee pour diverses acidites initiales de la solution aqueuse. Enfin, l'influence de la concentration des ions sulfate de la phase aqueuse sur l'extraction du beryllium a mis en evidence la formation en solution aqueuse de complexes anioniques de sulfate et de beryllium dont la constante de formation a ete evaluee. (auteur)

Preparation of copper-beryllium alloys from Indian beryl

International Nuclear Information System (INIS)

Paul, C.M.; Sharma, B.P.; Subba Rao, K.S.; Rajadhyaksha, M.G.; Sundaram, C.V.

1975-01-01

The report presents the results of laboratory scale investigations on the preparation of copper-beryllium and aluminium-beryllium master alloys starting from Indian beryl and adopting the fluoride process. The flow-sheet involves : (1) conversion of the Be-values in beryl into water soluble sodium beryllium fluoride (2) preparation of beryllium hydroxide by alkali treatment of aqueous Na 2 BeF 4 (3) conversion of Be(OH) 2 to (NH 4 ) 2 BeF 4 by treatment with NH 4 HF 2 (4) thermal decomposition of (NH 4 ) 2 BeF 4 to BeF 2 and (5) magnesium reduction of BeF 2 (with the addition of copper/aluminium) to obtain beryllium alloys. The method has been successfully employed for the preparation of Cu-Be master alloys containing about 8% Be and free of Mg on a 200 gm scale. An overall Be-recovery of about 80% has been achieved. Al-8% Be master alloys have also been prepared by this method. Toxicity and health hazards associated with Be are discussed and the steps taken to ensure safe handling of Be are described. (author)

Erosion of beryllium under ITER - Relevant transient plasma loads

Science.gov (United States)

Kupriyanov, I. B.; Nikolaev, G. N.; Kurbatova, L. A.; Porezanov, N. P.; Podkovyrov, V. L.; Muzichenko, A. D.; Zhitlukhin, A. M.; Gervash, A. A.; Safronov, V. M.

2015-08-01

Beryllium will be used as a armor material for the ITER first wall. It is expected that erosion of beryllium under transient plasma loads such as the edge-localized modes (ELMs) and disruptions will mainly determine a lifetime of the ITER first wall. This paper presents the results of recent experiments with the Russian beryllium of TGP-56FW ITER grade on QSPA-Be plasma gun facility. The Be/CuCrZr mock-ups were exposed to up to 100 shots by deuterium plasma streams (5 cm in diameter) with pulse duration of 0.5 ms and heat loads range of 0.2-0.5 MJ/m2 at different temperature of beryllium tiles. The temperature of Be tiles has been maintained about 250 and 500 °C during the experiments. After 10, 40 and 100 shots, the beryllium mass loss/gain under erosion process were investigated as well as evolution of surface microstructure and cracks morphology.

Reflector-moderated critical assemblies

International Nuclear Information System (INIS)

Paxton, H.C.; Jarvis, G.A.; Byers, C.C.

1975-07-01

Experiments with reflector-moderated critical assemblies were part of the Rover Program at the Los Alamos Scientific Laboratory (LASL). These assemblies were characterized by thick D 2 O or beryllium reflectors surrounding large cavities that contained highly enriched uranium at low average densities. Because interest in this type of system has been revived by LASL Plasma Cavity Assembly studies, more detailed descriptions of the early assemblies than had been available in the unclassified literature are provided. (U.S.)

Dose-effect relationships for the US radium dial painters

International Nuclear Information System (INIS)

Thomas, R.G.

1995-01-01

Dose-response data are presented from a large percentage of the US workers who were exposed to radium through the painting of luminous dials. The data in this paper are only from females, because very few males worked in this occupation. Log-normal analyses were done for radium-induced bone sarcomas and head carcinomas after the populations of the respective doses were first determined to be log-normally distributed. These populations included luminisers who expressed no radium-related cancerous condition. In this study of the female radium luminisers, the most important data concerning radiation protection are probably from workers who were exposed to radium but showed no cancer incidence. A total of 1391 subjects with average measured skeletal doses below 10 Gy are in this category. A primary purpose is to illustrate the strong case that 226,228 Ra is representative of those radionuclides that exemplify in humans a 'threshold' dose, a dose below which there has been no observed health effects on the exposed individual. Application of a threshold dose for radium deposited in the skeleton does not mean to imply that any other source of skeletal irradiation should be considered to follow a similar pattern. Second, a policy issue that begs for attention is the economic consequence of forcing radiation to appear as a highly toxic insult. It is time to evaluate the data objectively instead of formatting the extrapolation scheme beforehand and forcing the data to fit a preconceived pattern such as linearity through the dose-effect origin. In addition, it is time to re-evaluate (again) variations in background radiation levels throughout the world and to cease being concerned with, and regulating against, miniscule doses for which no biomedical effects on humans have ever been satisfactorily identified or quantified. (author)

Removal of radium from aqueous solutions using adsorbent produced from coconut coir pith

International Nuclear Information System (INIS)

Zalina Laili; Muhamat Omar; Mohd Zaidi Ibrahim; Esther Phillip; Mohd Abdul Wahab Yusof; Hassan, A.

2008-08-01

A study was conducted to evaluate the potential use of the coconut coir pith as an adsorbent for the removal of radium from aqueous solutions. Experiments to establish adsorptions as a function of pH and contact time were carried out. The results showed that radium adsorption are dependent upon pH and contact time of coconut coir pith with aqueous solutions. 70-80% of radium were adsorbed in the neutral to alkaline pH range. The amount of radium adsorbed also increased with contact time, reaching an optimum after 250 min. Thus, it can be concluded that the coconut coir pith has the potential to be used as an adsorbent in radium removal from aqueous solutions. (Author)

Denver Radium Boom and the Colorado School of Mines

International Nuclear Information System (INIS)

Hart, S.S.

1986-01-01

The November 7, 1985, Rocky Mountain News, proclaimed Radiation hot spot detected at Mines. This hot spot discovery was the result of investigative reports by a local television station, with follow-up radiation monitoring by the Colorado Department of Health. Not an isolated occurrence of alpha and gamma radiation contamination, the School of Mines discovery is only the latest in a five-year series of discoveries of radioactive waste disposal sites in the Denver metropolitan area. These discoveries have involved not only the Colorado Department of Health, but also the Environmental Protection Agency, at least five consulting firms, and numerous businessmen and homeowners. In 1982, the sites were combined into a single project called the Denver Radium Site and selected for clean-up under the Federal Superfund program. This paper reviews the historical aspects of these hot spots by describing the history of radium processing in Denver; early work of the Colorado School of Mines, National Radium Institute, the Golden Experiment Station, and other institutional research; and the commercial production of radium. 20 references

Status of beryllium development for fusion applications

International Nuclear Information System (INIS)

Billone, M.C.; Donne, M.D.; Macaulay-Newcombe, R.G.

1994-05-01

Beryllium is a leading candidate material for the neutron multiplier of tritium breeding blankets and the plasma facing component of first wall and divertor systems. Depending on the application, the fabrication methods proposed include hot-pressing, hot-isostatic-pressing, cold isostatic pressing/sintering, rotary electrode processing and plasma spraying. Product forms include blocks, tubes, pebbles, tiles and coatings. While, in general, beryllium is not a leading structural material candidate, its mechanical performance, as well its performance with regard to sputtering, heat transport, tritium retention/release, helium-induced swelling and chemical compatibility, is an important consideration in first-wall/blanket design. Differential expansion within the beryllium causes internal stresses which may result in cracking, thereby affecting the heat transport and barrier performance of the material. Overall deformation can result in loading of neighboring structural material. Thus, in assessing the performance of beryllium for fusion applications, it is important to have a good database in all of these performance areas, as well as a set of properties correlations and models for the purpose of interpolation/extrapolation

Critical parameters controlling irradiation swelling in beryllium

International Nuclear Information System (INIS)

Dubinko, V.I.

1995-01-01

Radiation effects in beryllium can hardly be explained within a framework of the conventional theory based on the bias concept due to elastic interaction difference (EID) between vacancies and self-interstitial atoms (SIAs) since beryllium belongs to hexagonal close-packed metals where diffusion has been shown to be anisotropic. Diffusional anisotropy difference (DAD) between point defects changes the cavity bias for their absorption and leads to dependence of the dislocation bias on the distribution of dislocations over crystallographic directions. On the other hand, the elastic interaction between point defects and cavities gives rise to the size and gas pressure dependencies of the cavity bias, resulting in new critical quantities for bubble-void transition effects at low temperature irradiation. In the present paper, we develop the concept of the critical parameters controlling irradiation swelling with account of both DAD and EID, and take care of thermal effects as well since they are of major importance for beryllium which has an anomalously low self-diffusion activation energy. Experimental data on beryllium swelling are analyzed on the basis of the present theory. (orig.)

Beryllium. Health hazards and their control. Pt. 2

International Nuclear Information System (INIS)

Lires, O.A.; Delfino, C.A.; Botbol, J.

1991-01-01

In this work (continuation of 'Beryllium' series) health hazards, toxic effects, limits of permissible atmospheric contamination and safe exposure to beryllium are described. Guidelines to the design, control operations and hygienic precautions of the working facilities are given. (Author) [es

Prevalence of technical mesothorium in self-luminous compounds used by New Jersey radium dial workers

International Nuclear Information System (INIS)

Keane, A.T.; Holtzmann, R.B.; Rundo, J.

1994-01-01

Forty-five sealed glass ampoules containing samples of radium dial paint prepared by the US Radium Corporation (USRC) and used by New Jersey dial workers in the period 1915--1928, were analyzed for radium-226 and radium-228 activity by high-resolution gamma-ray spectrometry. Radium-228 was found to be the dominant activating agent at the probable time of use in most of the sampled paints in which the ratio of radium-228 to radium-226 activity was determinable, the calculated radium-228 to radium-226 activity ratio in 1920 in these ranging from 7.2 to 10 (median 8.4), indicating that radium element chemically separated from commercialthorium ores (technical mesothorium) was used as the activator. Published isotopic activity ratios in USRC dial-paint samples that were appreciably in excess of those we found are shown invariably to be due to errors in calculation. Our results and information in the early literature suggested the hypothesis that dial paints used at USRC before July 1919 were activated with isotopically pure radium-226 whereas compounds used thereafter until the year 1925 were activated with technical mesothorium- Isotopic activity ratios predicted by the hypothesis compared well with median ratios observed in two groups of former workers. We conclude that inaccuracies in dates of hire and termination at USRC might well be the principal source of uncertainty in estimates of skeletal dose for former workers in whom the isotopic activity ratio has not been measured

Beryllium phonon spectrum from cold neutron measurements

International Nuclear Information System (INIS)

Bulat, I.A.

1979-01-01

The inelastic coherent scattering of neutrons with the initial energy E 0 =4.65 MeV on the spectrometer according to the time of flight is studied in polycrystalline beryllium. The measurements are made for the scattering angles THETA=15, 30, 45, 60, 75 and 90 deg at 293 K. The phonon spectrum of beryllium, i-e. g(w) is reestablished from the experimental data. The data obtained are compared with the data of model calculations. It is pointed out that the phonon spectrum of beryllium has a bit excessive state density in the energy range from 10 to 30 MeV. It is caused by the insufficient statistical accuracy of the experiment at low energy transfer

Breast cancer in female radium dial workers first employed before 1930

International Nuclear Information System (INIS)

Adams, E.E.; Brues, A.M.

1982-01-01

Female radium dial workers first employed before 1930 were analyzed for breast cancer mortality and incidence using method and rate tables described by Manson and the Mantel-Haenszel summary chi-square test for significance. Of 1180 located women, 736 were measured to estimate radium intake. This measured group was analyzed for breast cancer mortality and incidence according to four possible risk factors: radium intake dose, duration of employment, age at first exposure, and parity. The located women had a mortality ratio of 1.51 (p < 0.05). The measured women showed a significant excess of breast cancer incidence and mortality only among those women with a radium intake of 50 μCi or greater. Although not significant, incidence and mortality ratios were slightly higher for nulliparous women

Microbial accumulation of uranium, radium, and cesium

International Nuclear Information System (INIS)

Strandberg, G.W.; Shumate, S.E. II; Parrott, J.R. Jr.; North, S.E.

1981-05-01

Diverse microbial species varied considerably in their ability to accumulate uranium, cesium, and radium. Mechanistic differences in uranium uptake by Saccharomyces cerevisiae and Pseudomonas aeruginosa were indicated. S. serevisiae exhibited a slow (hours) surface accumulation of uranium which was subject to environmental factors, while P. aeruginosa accumulated uranium rapidly (minutes) as dense intracellular deposits and did not appear to be affected by environmental parameters. Metabolism was not required for uranium uptake by either organism. Cesium and radium were concentrated to a considerably lesser extent than uranium by the several species tested

ICT diagnostic method of beryllium welding quality

International Nuclear Information System (INIS)

Sun Lingxia; Wei Kentang; Ye Yunchang

2002-01-01

To avoid the interference of high density material for the quality assay of beryllium welding line, a slice by slice scanning method was proposed based upon the research results of the Industrial Computerized Tomography (ICT) diagnostics for weld penetration, weld width, off-centered deviation and weld defects of beryllium-ring welding seam with high density material inside

European Fusion Programme. ITER task T23: Beryllium characterisation. Progress report. Tensile tests on neutron irradiated and reference beryllium

International Nuclear Information System (INIS)

Moons, F.

1996-02-01

As part of the European Technology Fusion Programme, the irradiation embrittlement characteristics of the more ductile and isotopic grades of beryllium manufactured by Brush Wellman has been investigated using modern powder production and consolidation techniques . This study was initiated in support of the development and evaluation of beryllium as a neutron multiplier for the solid breeder blanket design concepts proposed for a DEMO fusion power reactor. Four different species of beryllium: S-200 F (vacuum hot pressed, 1.2 wt% BeO), S-200FH (hot isostatic pressed, 0.9 wt% BeO), S-65 (vacuum hot pressed, 0.6 wt% BeO), S-65H (hot isostatic pressed, 0.5 wt% BeO) have been compared. Three batches of the beryllium have been investigated, a neutron batch, a thermal control batch and a reference batch. Neutron irradiation has been performed at temperatures between 175 and 605 degrees Celsius up to a neutron fluence of 2.1 10 25 n.m -2 (E> 1 MeV) or 750 appm He. The results of the tensile tests are summarized

Radium in baggerspecie afkomstig uit het Rijnmondgebied. Resultaten over 2001

NARCIS (Netherlands)

Lembrechts J; Glastra P; Nissan LA; Overwater RMW; LSO

2002-01-01

The radium concentration was measured in 25 samples of harbour sludge taken in 2001 from the Rijnmond area (Rotterdam harbours and the Nieuwe Waterweg). High radium levels were found near the former discharge points of the phosphate ore processing plants, confirming the results of previous

5. IEA International workshop on beryllium technology for fusion. Book of abstracts

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-07-01

The collection includes the abstracts of reports presented to the 5-th IEA international workshop on beryllium technology for fusion. The themes of reports are as follows: status of beryllium technology for fusion in Russia; manufacturing and testing of Be armoured first wall mock-up for ITER; development of the process of diffusion welding of metals stainless steel-copper-beryllium into a single composite; some features of beryllium-laser beam interaction; the effect of irradiation dose on tritium and helium release from neutron irradiated beryllium; thermal properties of neutron irradiated Be{sub 12}Ti. The results of investigating the mechanical properties variation and swelling of beryllium under high temperature neutron irradiation are presented.

5. IEA International workshop on beryllium technology for fusion. Book of abstracts

International Nuclear Information System (INIS)

2001-01-01

The collection includes the abstracts of reports presented to the 5-th IEA international workshop on beryllium technology for fusion. The themes of reports are as follows: status of beryllium technology for fusion in Russia; manufacturing and testing of Be armoured first wall mock-up for ITER; development of the process of diffusion welding of metals stainless steel-copper-beryllium into a single composite; some features of beryllium-laser beam interaction; the effect of irradiation dose on tritium and helium release from neutron irradiated beryllium; thermal properties of neutron irradiated Be 12 Ti. The results of investigating the mechanical properties variation and swelling of beryllium under high temperature neutron irradiation are presented [ru

Natural Radium-226 accumulation in the human thyroid gland

International Nuclear Information System (INIS)

Simon, Steven L.; Ibrahim, Shawki A.; Barden, Adam O.; VanMiddlesworth, Lester

2008-01-01

Full text: Small amounts of Ra-226 and other radium isotopes routinely enter the human body through normal dietary intake and, in some cases, through occupational exposure. Currently accepted biokinetic models for radium in the human body assume a uniform distribution among all soft tissues and a short retention time in those tissues. These assumptions persist despite publications in the mid-1980s indicating that radium concentrations in tissue are related to calcium levels in each organ, implying that the thyroid gland could accumulate greater concentrations of radium isotopes than any other tissue. Moreover, the natural intake or production of sulfate or barium compounds in the body could serve to precipitate radium in the thyroid gland, thereby immobilizing it, with the result that the radionuclide stays resident for many years. Evidence of both accumulation and immobilization of Ra-226 in thyroids of grazing animals has been documented since the 1960s by one of us (LVM). Little is known, however, about the concentration and retention of radium in the human thyroid. Reported here, for the first time, are Ra-226 measurement data from about 100 human thyroids collected from over 95 persons with no known occupational exposure to radium with lifetime residences in the US and other countries, one person who routinely ingested a homeopathic preparation containing Ra-226, and three uranium miners. Sensitive measurements were made using the radon emanation technique. Regardless of the origin of the thyroid sample, Ra-226 activity was almost always detected above the detection limit of 0.65 mBq when at least 10 g of thyroid tissue were available. Our analyses to-date suggests a background concentration in human thyroids of about 0.1 ±0.01 Bq/kg, considerably greater than the commonly reported literature value of 0.003 Bq/kg in soft tissues. In addition, our measurements indicate concentrations of Ra-226 in the three uranium miners (whose exact job description was

Tritium behavior in ITER beryllium

International Nuclear Information System (INIS)

Longhurst, G.R.

1990-10-01

The beryllium neutron multiplier in the ITER breeding blanket will generate tritium through transmutations. That tritium constitutes a safety hazard. Experiments evaluating tritium storage and release mechanisms have shown that most of the tritium comes out in a burst during thermal ramping. A small fraction of retained tritium is released by thermally activated processes. Analysis of recent experimental data shows that most of the tritium resides in helium bubbles. That tritium is released when the bubbles undergo swelling sufficient to develop porosity that connects with the surface. That appears to occur when swelling reaches about 10--15%. Other tritium appears to be stored chemically at oxide inclusions, probably as Be(OT) 2 . That component is released by thermal activation. There is considerable variation in published values for tritium diffusion through the beryllium and solubility in it. Data from experiments using highly irradiated beryllium from the Idaho National Engineering Laboratory showed diffusivity generally in line with the most commonly accepted values for fully dense material. Lower density material, planned for use in the ITER blanket may have very short diffusion times because of the open structure. The beryllium multiplier of the ITER breeding blanket was analyzed for tritium release characteristics using temperature and helium production figures at the midplane generated in support of the ITER Summer Workshop, 1990 in Garching. Ordinary operation, either in Physics or Technology phases, should not result in the release of tritium trapped in the helium bubbles. Temperature excursions above 600 degree C result in large-scale release of that tritium. 29 refs., 10 figs., 3 tabs

Novel plasma source for safe beryllium spectral line studies in the presence of beryllium dust

Science.gov (United States)

Stankov, B. D.; Vinić, M.; Gavrilović Božović, M. R.; Ivković, M.

2018-05-01

Plasma source for beryllium spectral line studies in the presence of beryllium dust particles was realised. The guideline during construction was to prevent exposure to formed dust, considering the toxicity of beryllium. Plasma source characterization through determination of optimal working conditions is described. The necessary conditions for Be spectral line appearance and optimal conditions for line shape measurements are found. It is proven experimentally that under these conditions dust appears coincidently with the second current maximum. The electron density measured after discharge current maximum is determined from the peak separation of the hydrogen Balmer beta spectral line, and the electron temperature is determined from the ratios of the relative intensities of Be spectral lines emitted from successive ionized stages of atoms. Maximum values of electron density and temperature are measured to be 9.3 × 1022 m-3 and 16 800 K, respectively. Construction details and testing of the BeO discharge tube in comparison with SiO2 and Al2O3 discharge tubes are also presented in this paper.

Hydrodynamic instabilities in beryllium targets for the National Ignition Facility

Energy Technology Data Exchange (ETDEWEB)

Yi, S. A., E-mail: austinyi@lanl.gov; Simakov, A. N.; Wilson, D. C.; Olson, R. E.; Kline, J. L.; Batha, S. H. [Los Alamos National Laboratory, P.O. Box 1663, Los Alamos, New Mexico 87545 (United States); Clark, D. S.; Hammel, B. A.; Milovich, J. L.; Salmonson, J. D.; Kozioziemski, B. J. [Lawrence Livermore National Laboratory, P.O. Box 808, Livermore, California 94551 (United States)

2014-09-15

Beryllium ablators offer higher ablation velocity, rate, and pressure than their carbon-based counterparts, with the potential to increase the probability of achieving ignition at the National Ignition Facility (NIF) [E. I. Moses et al., Phys. Plasmas 16, 041006 (2009)]. We present here a detailed hydrodynamic stability analysis of low (NIF Revision 6.1) and high adiabat NIF beryllium target designs. Our targets are optimized to fully utilize the advantages of beryllium in order to suppress the growth of hydrodynamic instabilities. This results in an implosion that resists breakup of the capsule, and simultaneously minimizes the amount of ablator material mixed into the fuel. We quantify the improvement in stability of beryllium targets relative to plastic ones, and show that a low adiabat beryllium capsule can be at least as stable at the ablation front as a high adiabat plastic target.

Interaction of hydrogen and its isotopes with irradiated beryllium

International Nuclear Information System (INIS)

Tazhibaeva, I.L.; Shestakov, V.P.; Klepikov, A.Kh.; Pomanenko, O.G.; Chikhraj, E.V.; Kenzhin, E.A.; Zverev, V.V.; Kolbanenkov, A.N.

2000-01-01

In the article the results of experiments on hydrogen and its isotopes accumulation and gas-release from irradiated beryllium are presented. The irradiation was conducted at different media and temperatures in the RA and IVG.1M reactors. The measurements were carried out by thermal desorption method. Hydrogen release from beryllium samples saturated at different conditions were calculated. Dependence of hydrogen confinement character in beryllium from grain orientation in the sample, temperature and irradiation rate was revealed

Method for analysing radium in powder samples and its application to uranium prospecting

International Nuclear Information System (INIS)

Gong Xinxi; Hu Minzhi.

1987-01-01

The decayed daughter of Rn released from the power sample (soil) in a sealed bottle were collected on a piece of copper and the radium in the sample can be measured by counting α-particles with an Alphameter for uranium prospection, thus it is called the radium method. This method has many advantages, such as high sensitivity (the lowest limit of detection for radium sample per gram is 2.7 x 10 -15 g), high efficiency, low cost and easy to use. On the basis of measuring more than 700 samples taken along 20 sections in 8 deposits, the results show that the radium method is better than γ-measurement and equal to 210 Po method for the capability to descover anomalies. The author also summarizes the anomaly intensities of radium method, 210 Po method and γ-measurement respectively at the surface with deep blind ores, with or without surficial mineralization, and the figures of their profiles and the variation of Ra/ 210 Po ratios. According to the above-mentioned distinguishing features, the uranium mineralization located in deep and/or shallow parts can be distinguishd. The combined application of radium, 210 Po and γ-measurement methods may be regarded as one of the important methods used for anomaly assessment. Based on the experiments of the radium measurements with 771 stream sediments samples in an area of 100 km 2 , it is demonstrated that the radium mehtod can be used in the stages of uranium reconnaissance and prospecting

Immunological studies in the human radium population

International Nuclear Information System (INIS)

Lloyd, E.L.; Menon, M.

1976-01-01

Sera from patients carrying high body burdens of radium were evaluated by indirect immunofluorescence for antibodies reactive with tissue culture cell lines derived from five osteosarcomas and one malignant melanoma. These were compared with the sera from normal controls and patients with sarcomas and other malignancies. No significant difference could be detected between the number of reactions seen with the radium patients and the controls. By contrast, cross reactions between sera from all the tumor patients tested were greatly increased over the controls. With one osteosarcoma cell line, RPMI-41, 11 out of 12 of the tumor patients' sera reacted compared with 6 out of 17 for the controls. In addition, 30 out of 32 of the tumor patients' sera reacted with the malignant melanoma cell line compared with only 3 out of 12 for the controls. This suggests that if serum from a radium patient could be shown to cross react with a large number of carefully selected cell lines, the presence of a tumor might be suspected

Purification of mine water of radium - The implementation of the technology in a coal mine

International Nuclear Information System (INIS)

Chalupnik, S.

2002-01-01

In underground coal mines in the Upper Silesian Coal Basin there are inflows of highly mineralised waters containing radium isotopes. These waters cause radioactive pollution of the natural environment in mining areas. Therefore cleaning of saline waters of radium is very important. Two types of radium-bearing waters were distinguished - one type containing radium and barium ions, but no sulphates (type A) and another one in which radium and sulphate ions are present but no barium (type B). A very efficient and inexpensive method of purification of saline waters, of Ba 2+ and Ra 2+ ions was developed and implemented in two coal mines. As the result of used technology, based on application of phosphogypsum as the cleaning agent, a significant decrease of radium discharge was achieved - daily of about 120 MBq of 226 Ra and 80 MBq of 228 Ra. Another type of radium waters does not contain barium ions, but contains sulphate ions SO 4 2- . There is no carrier for co-precipitation of radium so radium is transported with discharged waters to main rivers. Different method of purification from radium must be applied for such waters. Laboratory and field experiments were performed, and a cleaning method was chosen. For purification of saline waters - waste products from other industrial processes are applied. The method of purification have been applied in full technical scale in coal mine with very good results - of about 6 m 3 /min of radium-bearing waters is cleaned. Whole this process takes place in underground old workings without any contact of mining crew with radioactive deposits, which are produced during the process. As a result radium amount released to the natural environment was significantly diminished - approximately of about 90 MBq of 226 Ra per day and 150 MBq of 228 Ra. (author)

Compatibility of stainless steels and lithiated ceramics with beryllium

Science.gov (United States)

Flament, T.; Fauvet, P.; Sannier, J.

1988-07-01

The introduction of beryllium as a neutron multiplier in ceramic blankets of thermonuclear fusion reactors may give rise to the following compatibility problems: (i) oxidation of Be by ceramics (lithium aluminate and silicates) or by water vapour; (ii) interaction between beryllium and austenitic and martensitic steels. The studies were done in contact tests under vacuum and in tests under wet sweeping helium. The contact tests under vacuum have revealed that the interaction of beryllium with ceramics seems to be low up to 700°C, the interaction of beryllium with steels is significant and is characterized by the formation of a diffusion layer and of a brittle Be-Fe-Ni compound. With type 316 L austenitic steel, this interaction appears quite large at 600°C whereas it is noticeable only at 700°C with martensitic steels. The experiments carried out with sweeping wet helium at 600°C have evidenced a slight oxidation of beryllium due to water vapour which can be enhanced in the front of uncompletely dehydrated ceramics.

Structure/property relationships in multipass GMA welding of beryllium.

Energy Technology Data Exchange (ETDEWEB)

Hochanadel, P. W. (Patrick W.); Hults, W. L. (William L.); Thoma, D. J. (Dan J.); Dave, V. R. (Vivek R.); Kelly, A. M. (Anna Marie); Pappin, P. A. (Pallas A.); Cola, M. J. (Mark J.); Burgardt, P. (Paul)

2001-01-01

Beryllium is an interesting metal that has a strength to weight ratio six times that of steel. Because of its unique mechanical properties, beryllium is used in aerospace applications such as satellites. In addition, beryllium is also used in x-ray windows because it is nearly transparent to x-rays. Joining of beryllium has been studied for decades (Ref.l). Typically joining processes include braze-welding (either with gas tungsten arc or gas metal arc), soldering, brazing, and electron beam welding. Cracking which resulted from electron beam welding was recently studied to provide structure/property relationships in autogenous welds (Ref. 2). Braze-welding utilizes a welding arc to melt filler, and only a small amount of base metal is melted and incorporated into the weld pool. Very little has been done to characterize the braze-weld in terms of the structure/property relationships, especially with reference to multipass welding. Thus, this investigation was undertaken to evaluate the effects of multiple passes on microstructure, weld metal composition, and resulting material properties for beryllium welded with aluminum-silicon filler metal.

The results of medical surveillance of beryllium production personnel

International Nuclear Information System (INIS)

Koviazin, A.; Urikh, A.; Kovianzina, L.

2004-01-01

The report presents results of surveillance of 1836 workers of beryllium production of Ulba Metallurgical Plant JSC with the acute and chronic forms of occupation diseases for 52 years of its operation. The dependence of acute and chronic occupation lesions on the protection degree is shown. It has been found out that, the risk of getting an occupation disease increases sharply at the moments of experimental works and at the time of reconstruction and some other extreme conditions in the production, that is supported by fixed lesions of eye mucous coat, skin and lung lesions. In this case, the readiness of people for their work in deleterious conditions and their personal responsibility for following the regulations of safety occupational standards plays a definite role. Therefore, the issues of protection are of paramount importance in prophylaxis both of acute and chronic exposure to beryllium. An influence of duration of service and occupation on chronic beryllium diseases is shown. A parallel between the lung beryllium disease and skin lesions by insoluble beryllium compounds is drawn for the first time. (author)

The uptake of uranium and radium from food and water in relation to calcium

International Nuclear Information System (INIS)

Wrenn, M.E.

1988-01-01

Observed ratios for dietary radium and calcium suggest that at least a 20 to 70 fold discrimination exists against radium uptake in the skeleton relative to calcium. It has been widely shown in many countries around the world that the relative radium to calcium ratio in the human skeleton varies from country to country, but within geographic areas, it appears to be relatively invariant with age. The ratio of radium-226 to calcium in intake, relative to the radium-226 to calcium value in the skeleton, is called the observed ratio, and varies over the world from a value of 0.013 to 0.039, with a mean of 0.024. In 1975, I inferred a mean observed ratio for uranium of 0.057 for the US. These findings suggest that man is in equilibrium with radium-226 with respect to the calcium in food and water. Most of the calcium would be ingested in diet, as would a significant amount, but not necessarily all, of the radium. The role of calcium for intake in water has not been examined

Spectrographic determination of impurities in beryllium oxide

International Nuclear Information System (INIS)

Paula Reino, L.C. de; Lordello, A.R.; Pereira, A.S.A.

1986-03-01

A method for the spectrographic determination of Al, B, Cd, Co, Cu, Cr, Fe, Mg, NaNi, Si and Zn in nuclear grade beryllium oxide has been developed. The determination of Co, Al, Na and Zn is besed upon a carrier distillation technique. Better results were obtained with 2% Ga 2 O 3 as carrier in beryllium oxide. For the elements B, Cd, Cu, Fe, Cr, Mg, Ni and Si the sample is loaded in a Scribner-Mullin shallow cup electrode, covered with graphite powder and excited in DC arc. The relative standard deviation values for different elements are in the range of 10 to 20%. The method fulfills requirements of precision and sensitivity for specification analysis of nuclear grade beryllium oxide.(Author) [pt

Progress report of preliminary studies of beryllium toxicity

Energy Technology Data Exchange (ETDEWEB)

Hodge, H.C.

1947-09-01

This document was prepared in connection with a symposium of beryllium poisoning held at the Saranac Laboratories and describes progress made and a research program aimed at characterizing the toxicity of beryllium. Seven individual papers in this document are separately indexed and cataloged for the database.

The effect of processing parameters on plasma sprayed beryllium for fusion applications

International Nuclear Information System (INIS)

Castro, R.G.; Stanek, P.W.; Jacobson, L.A.; Cowgill, D.F.; Snead, L.L.

1993-01-01

Plasma spraying is being investigated as a potential coating technique for applying thin (0.1--5mm) layers of beryllium on plasma facing surfaces of blanket modules in ITER and also as an in-situ repair technique for repairing eroded beryllium surfaces in high heat flux divertor regions. High density spray deposits (>98% of theoretical density) of beryllium will be required in order to maximize the thermal conductivity of the beryllium coatings. A preliminary investigation was done to determine the effect of various processing parameters (particle size, particle morphology, secondary gas additions and reduced chamber pressure) on the as-deposited density of beryllium. The deposits were made using spherical beryllium feedstock powder which was produced by centrifugal atomization at Los Alamos National Laboratory (LANL). Improvements in the as-deposited densities and deposit efficiencies of the beryllium spray deposits will be discussed along with the corresponding thermal conductivity and outgassing behavior of these deposits

The effect of processing parameters on plasma sprayed beryllium for fusion applications

International Nuclear Information System (INIS)

Castro, R.G.; Stanek, P.W.; Jacobson, L.W.; Cowgill, D.F.

1993-01-01

Plasma spraying is being investigated as a potential coating technique for applying thin (0.1-5mm) layers of beryllium on plasma facing surfaces of blanket modules in ITER and also as an in-situ repair technique for repairing eroded beryllium surfaces in high heat flux divertor regions. High density spray deposits (>98% of theoretical density) of beryllium will be required in order to maximize the thermal conductivity of the beryllium coatings. A preliminary investigation was done to determine the effect of various processing parameters (particle size, particle morphology, secondary gas additions and reduced chamber pressure) on the as-deposited density of beryllium. The deposits were made using spherical beryllium feedstock powder which was produced by centrifugal atomization at Los Alamos National Laboratory (LANL). Improvements in the as-deposited densities and deposit efficiencies of the beryllium spray deposits will be discussed along with the corresponding thermal conductivity and outgassing behavior of these deposits. (orig.)

Beryllium coating produced by evaporation-condensation method and some their properties

Energy Technology Data Exchange (ETDEWEB)

Pepekin, G.I.; Anisimov, A.B.; Chernikov, A.S.; Mozherinn, S.I.; Pirogov, A.A. [SRI SIA Lutch., Podolsk (Russian Federation)

1998-01-01

The method of vacuum evaporation-condensation for deposition of beryllium coatings on metal substrates, considered in the paper, side by side with a plasma-spray method is attractive fon ITER application. In particular this technique may be useful for repair the surface of eroded tiles which is operated in a strong magnetic field. The possibility of deposition of beryllium coatings with the rate of layer growth 0.1-0.2 mm/h is shown. The compatibility of beryllium coating with copper or stainless steel substrate is provided due to intermediate barrier. The results of examination of microstructure, microhardness, porosity, thermal and physical properties and stability under thermal cycling of beryllium materials are presented. The value of thermal expansion coefficient and thermal conductivity of condensed beryllium are approximately the same as for industrial grade material produced by powder mettalurgy technique. However, the condensed beryllium has higher purity (up to 99.9-99.99 % wt.). (author)

Technical aspects of the joint JET-ISX-B beryllium limiter experiment

International Nuclear Information System (INIS)

Edmonds, P.H.; Dietz, K.J.; Mioduszewski, P.K.; Watson, R.D.; Emerson, L.C.; Gabbard, W.A.; Goodall, D.; Simpkins, J.E.; Yarber, J.L.

1985-01-01

An experiment has been performed on the Impurity Study Experiment (ISX-B) tokamak to test beryllium as a limiter material. Beryllium is an attractive candidate for a limiter and has been proposed for use in the Joint European Torus (JET) experiment. A temperature-controlled, segmented, beryllium top-rail limiter was located inside the plasma radius described by the existing titanium limiters. An extended set of diagnostics was added for measurement of scrapeoff and limiter parameters. These included visible and infrared monitoring systems, probes, and surface analysis experiments. Tokamak experiments included parameter surveys of both Ohmically heated and neutral-beam-heated plasmas and an extended fluence test of the limiter. The most significant effect of operation with a beryllium limiter was the reduction in low-Z impurities caused by gettering action of beryllium deposited on the liner walls. The experiment required the design and implementation of contamination control apparatus and work procedures to prevent the accidental dispersion of beryllium dust

Beryllium mock-ups development and ultrasonic testing for ITER divertor conditions

International Nuclear Information System (INIS)

Barabash, V.R.; Bykov, V.A.; Giniyatulin, R.N.; Gervash, A.A.; Gurieva, T.M.; Egorov, K.E.; Komarov, V.L.; Korolkov, M.D.; Mazul, I.V.; Gitarsky, L.S.; Strulia, I.L.; Sizenev, V.S.; Pronyakin, V.T.

1995-01-01

At the present time beryllium is considered as the most suitable armour material for the ITER divertor application. Different types of Be-divertor mock-up construction are compared in the report. Two different technologies of beryllium tiles joining to a heat sink body are analysed: high temperature brazing and thermodiffusion bonding. The comparative analysis of different constructions has been performed on the basis of 2-D finite element calculation for temperatures and stresses. The main parameters and diagnostic capabilities of electron beam facility for HHF testing of beryllium mock-ups are described. The first results of HHF tests of ''beryllium-copper saddle-MAGT tube'' and ''beryllium-copper plate-SS body'' mock-ups are presented. The reasons of the damages during the HHF are analysed. The technique of ultrasonic testing of the thermodifussion bonding and brazing quality for beryllium-copper joints is presented. The recorded results are prepared in the form of ultrasound grams. The testing results are compared with the metallographic analysis. (orig.)

Preparation and characterization of beryllium doped organic plasma polymer coatings

International Nuclear Information System (INIS)

Brusasco, R.; Letts, S.; Miller, P.; Saculla, M.; Cook, R.

1995-01-01

We report the formation of beryllium doped plasma polymerized coatings derived from a helical resonator deposition apparatus, using diethylberyllium as the organometaric source. These coatings had an appearance not unlike plain plasma polymer and were relatively stable to ambient exposure. The coatings were characterized by Inductively Coupled Plasma Mass Spectrometry and X-Ray Photoelectron Spectroscopy. Coating rates approaching 0.7 μm hr -1 were obtained with a beryllium-to-carbon ratio of 1:1.3. There is also a significant oxygen presence in the coating as well which is attributed to oxidation upon exposure of the coating to air. The XPS data show only one peak for beryllium with the preponderance of the XPS data suggesting that the beryllium exists as BeO. Diethylberyllium was found to be inadequate as a source for beryllium doped plasma polymer, due to thermal decomposition and low vapor recovery rates

Radon/radium detection increases uranium drilling effectiveness

International Nuclear Information System (INIS)

Morse, R.H.; Cook, L.M.

1979-01-01

The use of portable radon detectors has become routine in reconnaissance uranium surveys where water and sediment samples are analyzed in field labs for radon and radium, and in detailed work where drill hole locations are pinpointed by field determinations of radon in soil gas from shallow holes. During the drilling program itself, however, very few operators are taking advantage of radon and radium analyses to decide whether a barren drill hole was a near miss or whether the immediate area can be written off. The technique, which is outlined here, is effective both above and below the water table

Neutron irradiation behavior of ITER candidate beryllium grades

Energy Technology Data Exchange (ETDEWEB)

Kupriyanov, I.B.; Gorokhov, V.A.; Nikolaev, G.N. [A.A.Bochvar All-Russia Scientific Research Inst. of Inorganic Materials (VNIINM), Moscow (Russian Federation); Melder, R.R.; Ostrovsky, Z.E.

1998-01-01

Beryllium is one of the main candidate materials both for the neutron multiplier in a solid breeding blanket and for the plasma facing components. That is why its behaviour under the typical for fusion reactor loading, in particular, under the neutron irradiation is of a great importance. This paper presents mechanical properties, swelling and microstructure of six beryllium grades (DshG-200, TR-30, TshG-56, TRR, TE-30, TIP-30) fabricated by VNIINM, Russia and also one - (S-65) fabricated by Brush Wellman, USA. The average grain size of the beryllium grades varied from 8 to 25 {mu}m, beryllium oxide content was 0.8-3.2 wt. %, initial tensile strength was 250-680 MPa. All the samples were irradiated in active zone of SM-3 reactor up to the fast neutron fluence (5.5-6.2) {center_dot} 10{sup 21} cm{sup -2} (2.7-3.0 dpa, helium content up to 1150 appm), E > 0.1 MeV at two temperature ranges: T{sub 1} = 130-180degC and T{sub 2} = 650-700degC. After irradiation at 130-180degC no changes in samples dimensions were revealed. After irradiation at 650-700degC swelling of the materials was found to be in the range 0.1-2.1 %. Beryllium grades TR-30 and TRR, having the smallest grain size and highest beryllium oxide content, demonstrated minimal swelling, which was no more than 0.1 % at 650-700degC and fluence 5.5 {center_dot} 10{sup 21} cm{sup -2}. Tensile and compression test results and microstructure parameters measured before and after irradiation are also presented. (author)

Erosion of beryllium under ITER – Relevant transient plasma loads

International Nuclear Information System (INIS)

Kupriyanov, I.B.; Nikolaev, G.N.; Kurbatova, L.A.; Porezanov, N.P.; Podkovyrov, V.L.; Muzichenko, A.D.; Zhitlukhin, A.M.; Gervash, A.A.; Safronov, V.M.

2015-01-01

Highlights: • We study the erosion, mass loss/gain and surface structure evolution of Be/CuCrZr mock-ups, armored with beryllium of TGP-56FW grade after irradiation by deuterium plasma heat load of 0.5 MJ/m 2 at 250 °C and 500 °C. • Beryllium mass loss/erosion under plasma heat load at 250 °C is rather small (no more than 0.2 g/m 2 shot and 0.11 μm/shot, correspondingly, after 40 shots) and tends to decrease with increasing number of shots. • Beryllium mass loss/erosion under plasma heat load at 500 °C is much higher (∼2.3 g/m 2 shot and 1.2 μm/shot, correspondingly, after 10 shot) and tends to decrease with increasing the number of shots (∼0.26 g/m 2 pulse and 0.14 μm/shot, correspondingly, after 100 shot). • Beryllium erosion value derived from the measurements of profile of irradiated surface is much higher than erosion value derived from mass loss data. - Abstract: Beryllium will be used as a armor material for the ITER first wall. It is expected that erosion of beryllium under transient plasma loads such as the edge-localized modes (ELMs) and disruptions will mainly determine a lifetime of the ITER first wall. This paper presents the results of recent experiments with the Russian beryllium of TGP-56FW ITER grade on QSPA-Be plasma gun facility. The Be/CuCrZr mock-ups were exposed to up to 100 shots by deuterium plasma streams (5 cm in diameter) with pulse duration of 0.5 ms and heat loads range of 0.2–0.5 MJ/m 2 at different temperature of beryllium tiles. The temperature of Be tiles has been maintained about 250 and 500 °C during the experiments. After 10, 40 and 100 shots, the beryllium mass loss/gain under erosion process were investigated as well as evolution of surface microstructure and cracks morphology

Erosion of beryllium under ITER – Relevant transient plasma loads

Energy Technology Data Exchange (ETDEWEB)

Kupriyanov, I.B., E-mail: igkupr@gmail.com [A.A. Bochvar High Technology Research Institute of Inorganic Materials, Rogova St. 5a, 123060 Moscow (Russian Federation); Nikolaev, G.N.; Kurbatova, L.A.; Porezanov, N.P. [A.A. Bochvar High Technology Research Institute of Inorganic Materials, Rogova St. 5a, 123060 Moscow (Russian Federation); Podkovyrov, V.L.; Muzichenko, A.D.; Zhitlukhin, A.M. [TRINITI, Troitsk, Moscow reg. (Russian Federation); Gervash, A.A. [Efremov Research Institute, S-Peterburg (Russian Federation); Safronov, V.M. [Project Center of ITER, Moscow (Russian Federation)

2015-08-15

Highlights: • We study the erosion, mass loss/gain and surface structure evolution of Be/CuCrZr mock-ups, armored with beryllium of TGP-56FW grade after irradiation by deuterium plasma heat load of 0.5 MJ/m{sup 2} at 250 °C and 500 °C. • Beryllium mass loss/erosion under plasma heat load at 250 °C is rather small (no more than 0.2 g/m{sup 2} shot and 0.11 μm/shot, correspondingly, after 40 shots) and tends to decrease with increasing number of shots. • Beryllium mass loss/erosion under plasma heat load at 500 °C is much higher (∼2.3 g/m{sup 2} shot and 1.2 μm/shot, correspondingly, after 10 shot) and tends to decrease with increasing the number of shots (∼0.26 g/m{sup 2} pulse and 0.14 μm/shot, correspondingly, after 100 shot). • Beryllium erosion value derived from the measurements of profile of irradiated surface is much higher than erosion value derived from mass loss data. - Abstract: Beryllium will be used as a armor material for the ITER first wall. It is expected that erosion of beryllium under transient plasma loads such as the edge-localized modes (ELMs) and disruptions will mainly determine a lifetime of the ITER first wall. This paper presents the results of recent experiments with the Russian beryllium of TGP-56FW ITER grade on QSPA-Be plasma gun facility. The Be/CuCrZr mock-ups were exposed to up to 100 shots by deuterium plasma streams (5 cm in diameter) with pulse duration of 0.5 ms and heat loads range of 0.2–0.5 MJ/m{sup 2} at different temperature of beryllium tiles. The temperature of Be tiles has been maintained about 250 and 500 °C during the experiments. After 10, 40 and 100 shots, the beryllium mass loss/gain under erosion process were investigated as well as evolution of surface microstructure and cracks morphology.

Testing of beryllium marker coatings in PISCES-B for the JET ITER-like wall

International Nuclear Information System (INIS)

Widdowson, A.; Baldwin, M.J.; Coad, J.P.; Doerner, R.P.; Hanna, J.; Hole, D.E.; Matthews, G.F.; Rubel, M.; Seraydarian, R.; Xu, H.

2009-01-01

Beryllium has been chosen as the first wall material for ITER. In order to understand the issues of material migration and tritium retention associated with the use of beryllium, a largely beryllium first wall will be installed in JET. As part of the JET ITER-like wall, beryllium tiles with marker coatings are proposed as a diagnostic tool for studying the erosion and deposition of beryllium around the vessel. The nominal structure for these coatings is a ∼10 μm beryllium surface layer separated from the beryllium tile by a 2-3 μm metallic inter-layer. Two types of coatings are tested here; one with a nickel inter-layer and one with a copper/beryllium mixed inter-layer. The coating samples were deposited by DC magnetron sputtering at General Atomics and were exposed to deuterium plasma in PISCES-B. The results of this testing show that the beryllium/nickel marker coating would be suitable for installation in JET.

Experimental studies and modeling of processes of hydrogen isotopes interaction with beryllium

Energy Technology Data Exchange (ETDEWEB)

Tazhibaeva, I.L.; Chikhray, Y.V.; Romanenko, O.G.; Klepikov, A.Kh.; Shestakov, V.P.; Kulsartov, T.V. [Science Research Inst. of Experimental and Theoretical Physics of Kazakh State Univ., Almaty (Kazakhstan); Kenzhin, E.A.

1998-01-01

The objective of this work was to clarify the surface beryllium oxide influence on hydrogen-beryllium interaction characteristics. Analysis of experimental data and modeling of processes of hydrogen isotopes accumulation, diffusion and release from neutron irradiated beryllium was used to achieve this purpose as well as the investigations of the changes of beryllium surface element composition being treated by H{sup +} and Ar{sup +} plasma glowing discharge. (author)

Radium-226 content and emanating power of some timepieces manufactured in the years 1926--1951

International Nuclear Information System (INIS)

Keane, A.T.; Huff, D.R.

Thirty-two radium-dial timepieces manufactured in the years 1926 to 1951 by a company in Connecticut were individually sealed in small steel cans for determination of radium-C ( 214 Bi) activity by γ-ray spectroscopy. Each can was counted within a few hours after sealing and again 5 or 6 days later; from the two observations, radium-C activities at time of sealing (nonemanating radium content) and at equilibrium (total radium content) were calculated. The mean radium-226 content of 22 pocket watches was 348 nCi (range, 159 to 606), and the mean emanating power (1-nonemanating Ra/total Ra) was 0.175 (range, 0.09 to 0.33). The mean radium-226 content of 9 wrist watches was 150 nCi (range, 54 to 449), and the mean emanating power was 0.242 (range, 0.12 to 0.34). The radium-226 content of the one small clock was 633 nCi, and its emanating power was 0.15. The concentration of radon-222 in the air of a sealed room of dimensions 3 x 3 x 3 m would be increased by about 3 pCi/l if a watch containing 400 nCi of radium-226 with an emanating power of 0.2 were left in the room for a few weeks. (U.S.)

Comparative uptake of thorium-230, radium-226, lead-210 and polonium-210 by plants

Energy Technology Data Exchange (ETDEWEB)

D' Souza, T J; Mistry, K B

1970-01-01

The entry and translocation of /sup 230/thorium, /sup 226/radium, /sup 210/lead, and /sup 210/polonium were examined in nutrient culture experiments. Strontium-89 was included for comparison. Red kidney beans (Phaseolus vulgaris L.) were treated for a period of 15 days. Results indicate that accumulation of /sup 230/thorium, /sup 210/lead and /sup 210/polonium occurs predominantly in roots and only very small amounts of these nuclides are translocated to shoots. Over comparable periods, the accumulation of /sup 226/radium in roots is 2-3 times lower than that of the other nuclides of uranium series. However, the most significant difference between /sup 226/radium and other nuclides is in the extent of their upward transport which for radium is 50-200 times greater. The amount of radium translocated to shoots is comparable to that of strontium. The present evidence of rapid transfer of /sup 226/radium to shoots suggests that among the nuclides examined, /sup 226/radium is likely to make the major contribution to radioactivity in aerial tissues of plants grown under conditions where root absorption is the principal route of entry of the nuclides.

Full-scale radium-removal system for a small community. Research report, 1 October 1985-30 September 1987

International Nuclear Information System (INIS)

Lauch, R.P.; Mangelson, K.A.

1988-08-01

A radium-removal treatment plant was constructed for the small community of Redhill Forest in the central mountains of Colorado. The plant consists of iron removal using oxidation, filtration, and settling; radium and hardness removal using ion exchange; and radium removal from the waste brine using Dow Chemical Company's Radium Selective Complexer (RSC). The raw water comes from deep wells and has naturally occuring radium and iron concentrations of about 30-40 pC/L and 7-10 mg/L, respectively, and is aerated before entering the main treatment plant to remove radon gas and carbon dioxide. A unique feature of the plant is the process that removes radium from the waste brine. The process removes only radium from the spent ion-exchange regeneration water by permanently complexing the radium on the RSC. The RSC is replaced when exhausted and sent to a final disposal site that is acceptable to state regulatory agencies. The overall plant reduces radium from about 35 pCi/L to less than 4 pCi/L. The RSC system has consistently removed over 99% of the radium from the spent ion exchange regenerant. The average inflow radium concentration to the RSC was about 1180 pCi/L, and the average effluent was about 9 pCi/L

Protection of air in premises and environment against beryllium aerosols

Energy Technology Data Exchange (ETDEWEB)

Bitkolov, N.Z.; Vishnevsky, E.P.; Krupkin, A.V. [Research Inst. of Industrial and Marine Medicine, St. Petersburg (Russian Federation)

1998-01-01

First and foremost, the danger of beryllium aerosols concerns a possibility of their inhalation. The situation is aggravated with high biological activity of the beryllium in a human lung. The small allowable beryllium aerosols` concentration in air poses a rather complex and expensive problem of the pollution prevention and clearing up of air. The delivery and transportation of beryllium aerosols from sites of their formation are defined by the circuit of ventilation, that forms aerodynamics of air flows in premises, and aerodynamic links between premises. The causes of aerosols release in air of premises from hoods, isolated and hermetically sealed vessels can be vibrations, as well as pulses of temperature and pressure. Furthermore, it is possible the redispersion of aerosols from dirty surfaces. The effective protection of air against beryllium aerosols at industrial plants is provided by a complex of hygienic measures: from individual means of breath protection up to collective means of the prevention of air pollution. (J.P.N.)

Cause of pitting in beryllium

International Nuclear Information System (INIS)

Kershaw, R.P.

1982-01-01

Light microscopy, bare-film radiography, secondary ion mass spectroscopy, electron microprobe and physical testing were used to examine beryllium specimens exhibiting a stratified, pitted, pattern after chemical milling. The objective was to find the cause of this pattern. Specimens were found to have voids in excess of density specification allowances. These voids are attributed, at least in part, to the sublimation of beryllium fluoride during the vacuum hot pressing operation. The origin of the pattern is attributed to these voids and etching out of fines and associated impurities. Hot isostatic pressing with a subsequent heat treatment close residual porosity and dispersed impurities enough to correct the problem

Thermal conductivity of beryllium under low temperature high dose neutron irradiation

International Nuclear Information System (INIS)

Chakin, V.P.; Latypov, R.N.; Suslov, D.N.; Kupriyanov, I.B.

2004-01-01

Thermal conductivity of compact beryllium of several Russian grades such as TE-400, TE-56, TE-30, TIP and DIP differing in the production technology, grain size and impurity content has been investigated. The thermal diffusivity of beryllium was measured on the disks in the initial and irradiated conditions using the pulse method in the range from room temperature to 200degC. The thermal conductivity was calculated using the table values for the beryllium thermal capacity. The specimens and beryllium neutron source fragments were irradiation in the SM reactor at 70degC and 200degC to a neutron fluence of (0.5-11.4)·10 22 cm -2 (E>0.1 MeV) and in the BOR-60 reactor at 400degC to 16·10 22 cm -2 (E>0.1MeV), respectively. The low-temperature irradiation leads to the drop decrease of the beryllium thermal conductivity and the effect depends on the irradiation parameters. The paper analyses the effect of irradiation parameters (temperature, neutron fluence), measurement temperature and structural factors on beryllium conductivity. The experiments have revealed that the short time post-irradiation annealing at high temperature results in partial reduction of the thermal conductivity of irradiated beryllium. (author)

Neutron activation analysis: Modelling studies to improve the neutron flux of Americium-Beryllium source

Energy Technology Data Exchange (ETDEWEB)

Didi, Abdessamad; Dadouch, Ahmed; Tajmouati, Jaouad; Bekkouri, Hassane [Advanced Technology and Integration System, Dept. of Physics, Faculty of Science Dhar Mehraz, University Sidi Mohamed Ben Abdellah, Fez (Morocco); Jai, Otman [Laboratory of Radiation and Nuclear Systems, Dept. of Physics, Faculty of Sciences, Tetouan (Morocco)

2017-06-15

Americium–beryllium (Am-Be; n, γ) is a neutron emitting source used in various research fields such as chemistry, physics, geology, archaeology, medicine, and environmental monitoring, as well as in the forensic sciences. It is a mobile source of neutron activity (20 Ci), yielding a small thermal neutron flux that is water moderated. The aim of this study is to develop a model to increase the neutron thermal flux of a source such as Am-Be. This study achieved multiple advantageous results: primarily, it will help us perform neutron activation analysis. Next, it will give us the opportunity to produce radio-elements with short half-lives. Am-Be single and multisource (5 sources) experiments were performed within an irradiation facility with a paraffin moderator. The resulting models mainly increase the thermal neutron flux compared to the traditional method with water moderator.

Technical issues and solutions on ITER first wall beryllium application. Industrial viewpoint

International Nuclear Information System (INIS)

Iwadachi, T.; Uda, M.; Ito, M.; Miyakawa, M.; Ibuki, M.

2004-01-01

Beryllium is selected as reference armor material of ITER primary first wall and is joined to the copper alloy heat sink such as CuCrZr or Dispersion Strengthened Copper (DSCu) Various joining technologies have been successfully developed and the manufacturing possibilities of large size first wall panels with beryllium armor has been demonstrated. Based on such results, further technical improvement is needed to reduce manufacturing cost and ensure the reliability of joining in actual size first wall. The technical issues to optimize the fabrication process of beryllium attachment were shown in this paper from an industrial point of view. Determination of the optimum size and the surface qualities of beryllium tiles are important issues in term of the material specification to ensure joining reliability and to reduce cost. The consolidation method and the finish machining methods of beryllium tiles are also critical in terms of material cost. These items should be determined by paying concern to the accommodation of the joining methods. The selections of slitting methods for attached beryllium have a great influence on fabrication cost. In the actual fabrication of beryllium attachment, safety provisions for exposure to beryllium in working environment and the recycling of the waste from the fabrication processes will be concerned sufficiently. (author)

Analysis of surface contaminants on beryllium and aluminum windows

International Nuclear Information System (INIS)

Gmur, N.F.

1987-06-01

An effort has been made to document the types of contamination which form on beryllium window surfaces due to interaction with a synchrotron radiation beam. Beryllium windows contaminated in a variety of ways (exposure to water and air) exhibited surface powders, gels, crystals and liquid droplets. These contaminants were analyzed by electron diffraction, electron energy loss spectroscopy, energy dispersive x-ray spectroscopy and wet chemical methods. Materials found on window surfaces include beryllium oxide, amorphous carbon, cuprous oxide, metallic copper and nitric acid. Aluminum window surface contaminants were also examined

Radiochemical determination and separation or total radium, 226Ra and 224Ra

International Nuclear Information System (INIS)

Suarez, J. A.; Gonzalez, J. A.; Pablo, M. A. de

1987-01-01

Radiochemical purification and separation of radium has been carried out and the determination of total radium solubilized in aqueous samples has been studied assuming that all the alpha emitters of the sample have their origin in the 226Ra and elements of its desintegration chain. Also, the activities of 22Ra and 226 Ra have been evaluated separately doing a measurement after the chemical separation of the radium and another one 10 days after. (Author) 9 refs

Abbreviated machining schedule for fabricating beryllium parts free of surface damage

International Nuclear Information System (INIS)

Beitscher, S.; Capes, J.F.; Leslie, W.W.; Luckow, J.R.; Riegel, R.L.

1979-01-01

This study was performed to develop a more economical method of machining damage-free beryllium components at Rocky Flats. The present method involves a 9-pass schedule of lathe turning followed by a chemical etch. Prototype beryllium hemispherical shell parts and cylindrical tensile specimens machined to simulate the parts were utilized in this study. The main investigative methods used to evaluate the amount of machining damage were metallography and tensile tests. It was found that damage-free parts could be produced by carefully controlled machining if the number of machining passes was reduced to 4 or even 3, if followed by the standard etching treatment. These findings were made on Select S-65 grade beryllium, and probably apply to other common grades of powder source beryllium but not necessarily to ingot-source beryllium. It is recommended that the 4-pass schedule becomes the standard method to produce damage-free beryllium derived from powder. Significant savings in time, labor, and equipment can be realized by this change in method without decreasing the quality of the product

A brownfield to greenfield success story: Denver Radium Superfund Site

International Nuclear Information System (INIS)

Baracani, E.; Bruskin, L.J.

1996-01-01

The Denver Radium Site consists of forty-nine separate sites divided into 11 operable units throughout the city of Denver, Colorado. The sites contained radioactive soils and residues (310,000 tons) from processing of radium in the early 1900s. The majority of the radioactive material was removed, transported by rail, and disposed offsite in Utah. During radiologic cleanup at the former Robinson Brick Company Site (ROBCO), (OU No. 4/5), metal contaminated soils from previous smelting operations were encountered. The Denver Radium Site was placed on the National Priorities List (NPL), and through cooperation of private parties, the state and federal governments, the land was cleaned up and restored to productive use

Remedial action of radium contaminated residential properties

International Nuclear Information System (INIS)

White, D.; Eng, J.

1986-01-01

Since November 1983, the New Jersey Department of Environmental Protection (NJDEP) and the US Environmental Protection Agency (USEPA) have been in the process of identifying properties in Montclair, Glen Ridge and West Orange, New Jersey, which were built over radium contaminated soil landfilled areas. Elevated indoor radon concentrations prompted the Centers for Disease Control (CDC) to issue a health advisory which included permanent remediation of radon progeny levels in excess of 0.02 Working Levels within two years of discovery. In order to expedite remedial action, NJDEP undertook a ten million dollar cleanup program. Remedial Action at the 12 residential properties encountered some unanticipated problems despite the efforts of numerous government agencies and their contractors to characterize the contamination as much as possible prior to remediation. Some of the unanticipated issues include contamination from other radionuclides, underestimation of removal volumes, and controversy over the transportation and disposal of the radium contaminated soil at a commercial facility in Nevada. This paper will review the approach taken by NJDEP to the remedial action for radium contaminated soil, discuss some of the issues encountered during the remedial action, and provide post remedial action data

Status of beryllium development for fusion applications

International Nuclear Information System (INIS)

Billone, M.C.; Macaulay-Newcombe, R.G.

1995-01-01

Beryllium is a leading candidate material for the neutron multiplier of tritium breeding blankets and the plasma-facing component of first-wall and divertor systems. Depending on the application, the fabrication methods proposed include hot-pressing, hot-isostatic-pressing, cold-isostatic-pressing/sintering, rotary electrode processing and plasma spraying. Product forms include blocks, tubes, pebbles, tiles and coatings. While, in general, beryllium is not a leading structural material candidate, its mechanical performance, as well as its performance with regard to sputtering, heat transport, tritium retention/release, helium-induced swelling and chemical compatibility, is an important consideration in first-wall/blanket design. Differential expansion within the beryllium causes internal stresses which may result in cracking, thereby affecting the heat transport and barrier performance of the material. Overall deformation can result in loading of neighboring structural material. Thus, in assessing the performance of beryllium for fusion applications, it is important to have a good database in all of these performance areas, as well as a set of properties correlations and models for the purpose of interpolation/extrapolation.In this current work, the range of anticipated fusion operating conditions is reviewed. The thermal, mechanical, chemical compatibility, tritium retention/release, and helium retention/swelling databases are then reviewed for fabrication methods and fusion operating conditions of interest. Properties correlations and uncertainty ranges are also discussed. In the case of the more complex phenomena of tritium retention/release and helium-induced swelling, fundamental mechanisms and models are reviewed in more detail. Areas in which additional data are needed are highlighted, along with some trends which suggest ways of optimizing the performance of beryllium for fusion applications. (orig.)

Eye changes induced by radium

International Nuclear Information System (INIS)

Taylor, G.N.; Lloyd, R.D.; Shabestari, Lorraine; Angus, Walter; Muggenburg, B.A.

1989-01-01

This report presents some features of the radium induced eye syndrome observed in beagles, including the prominence of intraocular pigmentary lesions and compares these with the results of rodent studies (Onychomys leucogaster) featuring a heavily pigmented uvea, and with the radiation syndrome reported in humans. (author)

Identification of an abnormal beryllium lymphocyte proliferation test

International Nuclear Information System (INIS)

Frome, Edward L.; Newman, Lee S.; Cragle, Donna L.; Colyer, Shirley P.; Wambach, Paul F.

2003-01-01

The potential hazards from exposure to beryllium or beryllium compounds in the workplace were first reported in the 1930s. The tritiated thymidine beryllium lymphocyte proliferation test (BeLPT) is an in vitro blood test that is widely used to screen beryllium exposed workers in the nuclear industry for sensitivity to beryllium. The clinical significance of the BeLPT was described and a standard protocol was developed in the late 1980s. Cell proliferation is measured by the incorporation of tritiated thymidine into dividing cells on two culture dates and using three concentrations of beryllium sulfate. Results are expressed as a 'stimulation index' (SI) which is the ratio of the amount of tritiated thymidine (measured by beta counts) in the simulated cells divided by the counts for the unstimulated cells on the same culture day. Several statistical methods for use in the routine analysis of the BeLPT were proposed in the early 1990s. The least absolute values (LAV) method was recommended for routine analysis of the BeLPT. This report further evaluates the LAV method using new data, and proposes a new method for identification of an abnormal or borderline test. This new statistical-biological positive (SBP) method reflects the clinical judgment that: (i) at least two SIs show a 'positive' response to beryllium; and (ii) that the maximum of the six SIs must exceed a cut-point that is determined from a reference data set of normal individuals whose blood has been tested by the same method in the same serum. The new data is from the Y-12 National Security Complex in Oak Ridge (Y-12) and consists of 1080 workers and 33 non-exposed control BeLPTs (all tested in the same serum). Graphical results are presented to explain the statistical method, and the new SBP method is applied to the Y-12 group. The true positive rate and specificity of the new method were estimated to be 86% and 97%, respectively. An electronic notebook that is accessible via the Internet was used in

Beryllium data base for in-pile mockup test on blanket of fusion reactor, (1)

Energy Technology Data Exchange (ETDEWEB)

Kawamura, Hiroshi; Ishitsuka, Etsuo (Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment); Sakamoto, Naoki; Kato, Masakazu; Takatsu, Hideyuki.

1992-11-01

Beryllium has been used in the fusion blanket designs with ceramic breeder as a neutron multiplier to increase the net tritium breeding ratio (TBR). The properties of beryllium, that is physical properties, chemical properties, thermal properties, mechanical properties, nuclear properties, radiation effects, etc. are necessary for the fusion blanket design. However, the properties of beryllium have not been arranged for the fusion blanket design. Therefore, it is indispensable to check and examine the material data of beryllium reported previously. This paper is the first one of the series of papers on beryllium data base, which summarizes the reported material data of beryllium. (author).

Spectrochemical determination of beryllium and lithium in stream sediments

International Nuclear Information System (INIS)

Gallimore, D.L.; Hues, A.D.; Palmer, B.A.; Cox, L.E.; Simi, O.R.; Bieniewski, T.M.; Steinhaus, D.W.

1979-11-01

A spectrochemical method was developed to analyze 200 or more samples of stream sediments per day for beryllium and lithium. One part of ground stream sediment is mixed with two parts graphite-SiO 2 buffer, packed into a graphite electrode, and excited in a direct-current arc. The resulting emission goes to a 3.4-m, direct-reading, Ebert spectrograph. A desk-top computer system is used to record and process the signals, and to report the beryllium and lithium concentrations. The limits of detection are 0.2 μg/g for beryllium and 0.5 μg/g for lithium. For analyses of prepared reference materials, the relative standard deviations were 16% for determining 0.2 to 100 μg/g of beryllium and 15% for determining 0.5 to 500 μg/g of lithium. A correction is made for vanadium interference

Behaviour of radium isotopes released with brines and sediments from coal mines in Poland

International Nuclear Information System (INIS)

Wysocka, M.; Chalupnik, S.; Mielnikow, A.; Lebecka, J.; Skubacz, K.

1998-01-01

Saline waters occurring in underground coal mines in Poland often contain natural radioactive isotopes, mainly 226 Ra from uranium series and 228 Ra from thorium series. Approximately 40% of total amount of radium remains underground in a form of radioactive deposits, but 225 MBq of 226 Ra and 380 MBq of 228 Ra are released daily to the rivers with mine effluents. Technical measures as spontaneous precipitation of radium in gobs, decreasing of amounts of water inflowing into underground working etc. have been undertaken in several coal mines and in the result total amount of radium released to the surface waters diminished by about 60% during last 5-6 years. Mine waters can cause a severe impact on the natural environment. The enhancement of radium concentration in river waters, bottom sediments and vegetation is observed. Sometimes radium concentration in rivers exceeds 0.7 kBq/m 3 , which is due to Polish law a permissible level for liquid radioactive waste. It was necessary to undertake investigations for development the methods of the purification of mine waters from radium. The radium balance in effluents has been calculated and a map of radioactive contamination of river waters have been prepared. Solid wastes with enhanced natural radioactivity have been produced in huge amounts in energy and coal industries in Poland. There are two main sources of these waste products. As a result of combustion of coal in power plants low radioactive waste materials are produced, with 226 Ra concentration seldom exceeding few hundreds of Bq/kg. Different situation is be observed in coal mines, where as a result of precipitation of radium from radium-bearing waters radioactive deposits are formed. Sometimes natural radioactivity of such materials is very high, in case of scaling from coal mines radium concentration may reach 4x10 5 Bq/kg - similar activity as for 3% uranium ore. Therefore maintenance of solid waste with technologically enhanced natural radioactivity (TENR

New facility for post irradiation examination of neutron irradiated beryllium

International Nuclear Information System (INIS)

Ishitsuka, Etsuo; Kawamura, Hiroshi

1995-01-01

Beryllium is expected as a neutron multiplier and plasma facing materials in the fusion reactor, and the neutron irradiation data on properties of beryllium up to 800 degrees C need for the engineering design. The acquisition of data on the tritium behavior, swelling, thermal and mechanical properties are first priority in ITER design. Facility for the post irradiation examination of neutron irradiated beryllium was constructed in the hot laboratory of Japan Materials Testing Reactor to get the engineering design data mentioned above. This facility consist of the four glove boxes, dry air supplier, tritium monitoring and removal system, storage box of neutron irradiated samples. Beryllium handling are restricted by the amount of tritium;7.4 GBq/day and 60 Co;7.4 MBq/day

Multiple myeloma, leukemia, and breast cancer among the US radium dial workers

International Nuclear Information System (INIS)

Stebbings, J.H.; Lucas, H.F.; Stehney, A.F.

1984-01-01

The relationships of radium exposure to mortality from multiple myeloma, leukemia, and breast cancer were studied in three cohorts of female dial workers defined by year of first employment. A three-fold excess risk of multiple myeloma occurred in the pre-1930 cohort; however, analyses of body burdens and durations of employment suggest that external radiation was more likely to have been responsible than was internal radium. Leukemia incidence and mortality have not been elevated overall among the female dial workers, either in the pre-1930 or the post-1930 cohorts, but cases have tended to occur early and in subjects with higher body burdens of radium. Extensive analyses of breast cancer data have uncovered several observations weighing against a causal interpretation of the association between radium body burdens and breast cancer

Microplasticity in hot-pressed beryllium

International Nuclear Information System (INIS)

Plane, D.C.; Bonfield, W.

1977-01-01

Closed hysteresis loops measured in the microstrain region of hot pressed, commercially pure, polycrystalline beryllium are correlated with a dislocation - impurity atom, energy dissipating mechanism. (author)

Movement of liquid beryllium during melt events in JET with ITER-like wall

International Nuclear Information System (INIS)

Sergienko, G; Huber, A; Brezinsek, S; Coenen, J W; Mertens, Ph; Philipps, V; Samm, U; Arnoux, G; Matthews, G F; Nunes, I; Riccardo, V; Sirinelli, A; Devaux, S

2014-01-01

The ITER-like wall recently installed in JET comprises solid beryllium limiters and a combination of bulk tungsten and tungsten-coated carbon fibre composite divertor tiles without active cooling. During a beryllium power handling qualification experiment performed in limiter configuration with 5 MW neutral beam injection input power, accidental beryllium melt events, melt layer motion and splashing were observed locally on a few beryllium limiters in the plasma contact areas. The Lorentz force is responsible for the observed melt layer movement. To move liquid beryllium against the gravity force, the current flowing from the plasma perpendicularly to the limiter surface must be higher than 6 kA m −2 . The thermo-emission current at the melting point of beryllium is much lower. The upward motion of the liquid beryllium against gravity can be due to a combination of the Lorentz force from the secondary electron emission and plasma pressure force. (paper)

The determination of radium-226 in the tailings of gold mines and their environment

International Nuclear Information System (INIS)

Malan, J.J.

1981-10-01

Radium-226, a daughter product in the uranium-238 decay series, is present in ore mined for the production of both gold and uranium. In this way the radium-226 finds its way into the tailings of mines and is therefore present in all the mine sand dumps and slimes dams in the Republic. Although this radium-226 is in a relatively stable and practically insoluble matrix, it is nevertheless possible for it to migrate from such slimes dams or sand dumps under the influence of various mechanisms. In order to make a survey in these mining environments, it was necessary to adapt an existing emanometric method. In this method radium-226 is co-precipitated from 5 dm 3 water samples with barium sulphate. An investigation was carried out on the recoverability of the radium-226 in this way and it was found that the best results were achieved at a pH of 1 with co-precipitation from a homogenous or a simulated homogenous medium. The barium sulphate precipitate was dissolved by a sodium carbonate fusion with the resulting carbonates dissolving in hydrochloric acid. The back-ground reading due to the presence of radium-266 in the reagents used and the radium-226 slightly contaminating the glassware, was determined with blank measurements. This mean background value was used to determine the detection limit. In the survey, samples of water, slimes, sand and sediment were taken in the main gold-mining areas of the RSA. From the results of the survey it appears that radium-226 is definitely present in the abovementioned environments, but that the concentrations are very low. It was, furthermore, evident that, in contrast with the relatively high concentrations measured near the pollution source, the measured quantity of radium-226 decreases rapidly with increasing distance from the source

Recent cases of radium-induced malignancy

International Nuclear Information System (INIS)

Brues, A.M.

1978-01-01

Five cases of malignant disease attributed to radium in patients with measured body burdens have been discovered since 1974, including three bone sarcomas and two mastoid carcinomas. Pertinent findings in these cases are summarized here

Radium-226 in vegetation and substrates at inactive uranium mill sites

Energy Technology Data Exchange (ETDEWEB)

Marple, M.L.

1980-01-01

Results of a study of the content of radium-226 in plants growing on inactive uranium mill tailings sites in the Four Corners Region of the southwestern United States and in plants grown under greenhouse conditions with minimal surficial contamination are reported. Field plant samples and associated substrates were analyzed from two carbonate tailings sites in the Grants Mineral Belt of New Mexico. Radium activities in air-cleaned samples ranged from 5 to 368 pCi/g (dry weight) depending on species and location: activities in plants growing on local soils averaged 1.0 pCi/g. The talings and local soils contain 140 to 1400 pCi/g and 2.1 pCi/g, respectively. An evaluation of cleaning methods on selected samples showed that from 17 to 79% of the radium activity measured in air-cleaned samples was due to surficial contamination, which varied with species and location. A survey of 18 inactive uranium mill sites in the Four Corners Region was performed. Radium activity in plant tissues from nine species ranged from 2 to 210 pCi/g on bare tailings and from 0.3 to 30 pCi/g on covered tailings The radium content in most of the soil overburdens on the covered tailings piles was 10 to 17 pCi/g. An experiment was performed to measure radium-226 uptake by two species grown on tailings covered with a shallow (5 cm) soil layer. A grass, Sporobolus airoides (alkali sacaton) and a shrub, Atriplex canescens (four-wing saltbush), were studied. The tailings were a mixture of sands and slimes from a carbonate pile. The tailings treatments were plants grown in a soil cover over tailings; the controls were plants grown only in soil. Three soil types, dune sand, clay loam, and loam, were used. The radium activity of the plant tissue from the tailings treatment compared to that of the appropriate control was 1 to 19 times greater for the grass and 4 to 27 times greater for the shrub.

Radium-226 in vegetation and substrates at inactive uranium mill sites

International Nuclear Information System (INIS)

Marple, M.L.

1980-01-01

Results of a study of the content of radium-226 in plants growing on inactive uranium mill tailings sites in the Four Corners Region of the southwestern United States and in plants grown under greenhouse conditions with minimal surficial contamination are reported. Field plant samples and associated substrates were analyzed from two carbonate tailings sites in the Grants Mineral Belt of New Mexico. Radium activities in air-cleaned samples ranged from 5 to 368 pCi/g (dry weight) depending on species and location: activities in plants growing on local soils averaged 1.0 pCi/g. The talings and local soils contain 140 to 1400 pCi/g and 2.1 pCi/g, respectively. An evaluation of cleaning methods on selected samples showed that from 17 to 79% of the radium activity measured in air-cleaned samples was due to surficial contamination, which varied with species and location. A survey of 18 inactive uranium mill sites in the Four Corners Region was performed. Radium activity in plant tissues from nine species ranged from 2 to 210 pCi/g on bare tailings and from 0.3 to 30 pCi/g on covered tailings The radium content in most of the soil overburdens on the covered tailings piles was 10 to 17 pCi/g. An experiment was performed to measure radium-226 uptake by two species grown on tailings covered with a shallow (5 cm) soil layer. A grass, Sporobolus airoides (alkali sacaton) and a shrub, Atriplex canescens (four-wing saltbush), were studied. The tailings were a mixture of sands and slimes from a carbonate pile. The tailings treatments were plants grown in a soil cover over tailings; the controls were plants grown only in soil. Three soil types, dune sand, clay loam, and loam, were used. The radium activity of the plant tissue from the tailings treatment compared to that of the appropriate control was 1 to 19 times greater for the grass and 4 to 27 times greater for the shrub

Eliminating radium from uranium mill acid effluent with barium chloride-sodium carbonate precipitation

International Nuclear Information System (INIS)

Xiao Jiayuan

1998-01-01

The eliminating radium procedure, barium chloride-sodium carbonate-sand filtering, being used, radium can be eliminated to 3.7 x 10 -2 Bq/L order of magnitude from uranium mill acid effluents which contain 3.7 Bq/L Ra and pH 6∼9 when Ba 2+ is added by 3∼5 mg per litre, Na 2 CO 3 5mg. The radium elimination rate is more than 90%

About kinetics of paramagnetic radiation malformations in beryllium ceramics

International Nuclear Information System (INIS)

Polyakov, A.I.; Ryabinkin, Yu.A.; Zashkvara, O.V.; Bitenbaev, M.I.; Petukhov, Yu.V.

1999-01-01

This paper [1] specifies that γ-radiation of the beryllium-oxide-based ceramics results in development of paramagnetic radiation malformations emerging the ESR spectrum in form of doublet with the splitting rate of oestrasid Δ∼1.6 and g-factor of 2.008. This report presents evaluation outcomes of dependence of paramagnetic radiation malformations concentration in beryllium ceramics on gamma-radiation dose ( 60 Co) within the range of 0-100 Mrad. Total paramagnetic parameters of beryllium ceramics in the range 0-100 Mrad of gamma-radiation dose varied slightly, and were specified by the first type of paramagnetic radiation malformations

Reducing the cost of S-65C grade beryllium for ITER first wall applications

International Nuclear Information System (INIS)

Kaczynski, D.; Sato, K.; Savchuk, V.V.; Shestakov, V.P.

2004-01-01

Beryllium is the current material of choice for plasma-facing components in ITER. The present design is for 10 mm thick beryllium tiles bonded to an actively cooled copper substrate. Brush Wellman grade S65C beryllium is preferred grade off beryllium for these tiles. S65C has the best resistance to low-cycle thermal fatigue than any other beryllium grad in the world. S65C grade beryllium has been successfully deployed in fusion reactors for more than two decades, most recently in the JET reactor. This paper will detail a supply chain to produce the most cost-effective S65C plasma facing components for ITER. This paper will also propose some future work too demonstrate the best technology for bonding beryllium to copper. (author)

Controlling Beryllium Contaminated Material And Equipment For The Building 9201-5 Legacy Material Disposition Project

International Nuclear Information System (INIS)

Reynolds, T.D.; Easterling, S.D.

2010-01-01

This position paper addresses the management of beryllium contamination on legacy waste. The goal of the beryllium management program is to protect human health and the environment by preventing the release of beryllium through controlling surface contamination. Studies have shown by controlling beryllium surface contamination, potential airborne contamination is reduced or eliminated. Although there are areas in Building 9201-5 that are contaminated with radioactive materials and mercury, only beryllium contamination is addressed in this management plan. The overall goal of this initiative is the compliant packaging and disposal of beryllium waste from the 9201-5 Legacy Material Removal (LMR) Project to ensure that beryllium surface contamination and any potential airborne release of beryllium is controlled to levels as low as practicable in accordance with 10 CFR 850.25.

Atlas of hot isostatic beryllium powder pressing diagrams

International Nuclear Information System (INIS)

Stoev, P.I.; Papirov, I.I.; Tikhinskij, G.F.; Vasil'ev, A.A.

1995-01-01

Diagrams of hot isotopic pressing (HIP) of beryllium powder with different grain size in a wide range of pressing parameters are built by mathematical modeling methods. The HIP diagrams presented are divided into 3 groups: parametric dependencies D=f(P,T); technological HIP diagrams; compacting mechanisms. The created data bank permits to optimise beryllium powder HIP with changing parameters. 4 refs., 23 figs

Corrosion of beryllium exposed to celotex and water

International Nuclear Information System (INIS)

Hill, M.A.; Butt, D.P.; Lillard, R.S.

1997-01-01

Celotex is a commercial rigid cellulose fiberboard product primarily used in the building construction industry. Currently celotex is being used as a packing material in AL-R8 containers. Ion chromatography of celotex packing material at Lawrence Livermore National Laboratory (LLNL) has indicated that this material contains aggressive anions, including chloride, which may accelerate corrosion. It is well known that beryllium is susceptible to pitting corrosion when exposed to chloride containing environments. Levy noted pitting in beryllium at the open circuit potential when exposed to 0.1 M NaCl solution. This investigation attempts to evaluate the potential risk of accelerated beryllium corrosion from celotex and water which may occur naturally when celotex dust comes into contact with moisture from the atmosphere

A diethylhydroxylaminate based mixed lithium/beryllium aggregate

Energy Technology Data Exchange (ETDEWEB)

Berger, Raphael J.F. [Paris-Lodron Universitaet Salzburg (Austria). Fachbereich fuer Materialwissenschaften und Physik; Jana, Surajit [Asansol Girls College, West-Bengal (India). Dept. of Chemistry; Froehlich, Roland [Muenster Univ. (Germany). Organisch-Chemisches Inst.; Mitzel, Norbert W. [Bielefeld Univ. (Germany). Anorganische Chemie und Strukturchemie

2015-07-01

A mixed lithium/beryllium diethylhydroxylaminate compound containing {sup n}butyl beryllium units of total molecular composition {sup n}Be(ONEt{sub 2}){sub 2} [(LiONEt{sub 2}){sup 2} {sup n}BuBeONEt{sub 2}]{sub 2} (1) was isolated from a reaction mixture of {sup n}butyl lithium, N,N-diethylhydroxylamine and BeCl{sub 2} in diethylether/thf. The crystal structure of 1 has been determined by X-ray diffraction. The aggregate is composed of two ladder-type subunits connected in a beryllium-centered distorted tetrahedron of four oxygen atoms. Only the lithium atoms are engaged in coordination with the nitrogen donor atoms. The DFT calculations support the positional occupation determined for Li and Be in the crystal structure. The DFT and the solid-state structure are in excellent agreement, indicating only weak intermolecular interactions in the solid state. Structural details of metal atom coordination are discussed.

Determination of radium-226 by high-resolution alpha spectrometry

International Nuclear Information System (INIS)

Sill, C.W.

1983-01-01

The determination of radium-226 by alpha spectrometry has been investigated critically to determine experimental conditions under which high resolution and accurate and reliable results can be obtained. Refractory solids such as soils, ores, and tailings from uranium mills are dissolved completely by fusion with potassium fluoride in the presence of barium-133 tracer. The fluoride cake is then transposed with sulfuric acid to a pyrosulfate fusion with simultaneous volatilization of all silica and fluoride. Radium is precipitated with barium already present in the sample by addition of lead perchlorate to a dilute hydrochloric acid solution of the pyrosulfate cake. The resulting insoluble sulfates are dissolved in an alkaline solution of diethylenetriaminepentaacetic acid, and the radium and barium sulfates are reprecipitated with acetic acid. The precipitate is mounted on a membrane filter and analyzed by alpha spectrometry. Water samples are partially evaporated and treated similarly. Resolution of the subsequent alpha spectra is much better than has been achieved previously from barium sulfate, and is almost as good as is obtainable with actinides electrodeposited on polished steel plates. The resolution is about 60 keV full-width-half-maximum with 100 μg of barium on a 1-inch filter with a 450 mm 2 detector at 20% counting efficiency. Recovery is about 97% and accuracy is generally as good as the counting statistics obtained will permit. Grossly inaccurate results can be obtained under certain conditions when barium-133 tracer is used to determine the chemical yield of radium-226. Severe contamination of the surface-barrier detector by polonium-210 and by recoil products of the radium isotopes being counted is demonstrated, amd methods for virtual elimination of both problems are discussed

Survival times of pre-1950 US women radium dial workers

International Nuclear Information System (INIS)

Stehney, A.F.

1994-01-01

Survival times of US women radium dial workers to the end of 1989 were examined by life table methods. Included were 1301 women rust employed before 1930 and 1242 first employed in 1930-1949. Expected numbers of deaths were estimated from age- and time-specific death rates for US white females. In the early group, 85 deaths from the well-known radium-induced cancers - bone sarcomas and head carcinomas - were observed, but only 724 deaths from aH other causes were observed vs 755 expected. Life shortening (±S.E.) of 1.8 ±0.5 y compared to the general population of US white females was calculated from the time distribution of all deaths in the pre-1930 group. In the 1930--1949 group, 350 deaths were observed vs 343 expected and no bone sarcomas or head carcinomas occurred. Among women who survived at least 2 y after rust measurement of body radium, a significant excess of observed vs expected deaths was found only for radium intakes greater than 1.85 MBq of 226 Ra + 228 Ra, and no trend of deaths or reduction of life expectancy was found with length of employment

Feasibility demonstration of consolidating porous beryllium/carbon structures. Final report

International Nuclear Information System (INIS)

Browning, M.J.; Hoover, G.E.; Mueller, J.J.; Hanes, H.D.

1977-01-01

A preliminary feasibility study was initiated to determine if porous beryllium structures could be fabricated by consolidating beryllium-coated microballoons into a rigid structure. The target specifications were to coat nominally 1-mm diameter microspheres with 0.5-mil beryllium coatings and then bond into a structure. Because of the very short time period, it was agreeable to use existing or quickly-available materials. The general approach was to apply coatings to carbon or quartz microspheres. Physical vapor deposition and ''snow-balling'' of fine beryllium powder were the two methods investigated. Once the particles were coated, HIP (pressure bonding) and pressureless sintering were to be investigated as methods for consolidating the microballoons. A low level of effort was to be spent to look at means of fabricating an all-carbon structure

Beryllium reflectors for research reactors. Review and preliminary finite element analysis

Energy Technology Data Exchange (ETDEWEB)

Bejarano, Pablo S; Cocco, Roxana G., E-mail: rcocco@invap.com.ar [INVAP S.E., Rio Negro (Argentina)

2012-03-15

Beryllium is used in numerous research reactors to moderate neutron energy and to reflect neutrons back into the core, thus intensifying the thermal neutron flux. However, beryllium is degraded by radiation damage, as a result of both displacement and transmutation. Displacement damage leads to point defect clustering, irradiation hardening and embrittlement. Transmutation produces helium, which results in high levels of gas and swelling, even at low temperatures. A brief state-of-the-art review on the use of reflector assemblies reveals that each user has adopted a different method for overcoming problems related to swelling: strengthening, cracking and distortion. In the present work a preliminary study about the geometry influence on the reflector assembly behavior was performed by a Finite Element Analysis (FEA). A simplified study was made varying its geometry in height, thickness and width. The results showed that the most influencing parameter in avoiding distortion due to swelling is firstly the reflector's assembly height, H; secondly its thickness, L, and lastly its angle/width, {theta}. These results contribute to the understanding of distortion behavior and the stresses generated in a simple geometry Be bar subjected to radiation, which can be a useful tool for mechanical design of more complex components. (author)

Proceedings of the third IEA international workshop on beryllium technology for fusion

International Nuclear Information System (INIS)

Kawamura, Hiroshi; Okamoto, Makoto

1998-01-01

This report is the Proceedings of the Third International Energy Agency International Workshop on Beryllium Technology for Fusion. The workshop was held on October 22-24, 1997, at the Sangyou Kaikan in Mito City with 68 participants who attended from the Europe, the Russian Federation, the Kazakstan, the United States and Japan. The topics for papers were arranged into 9 sessions; beryllium applications for ITER, production and characterization, chemical compatibility and corrosion, forming and joining, plasma/tritium interactions, beryllium coating, first wall applications, neutron irradiation effects, health and safety. To utilize beryllium in the pebble type blanket, a series of discussions were intensified in multiple view points such as the swelling, He/T release from beryllium pebble irradiated up to high He content, effective thermal conductivity, tritium permeation and coating, and fabrication cost, and so on. As the plasma facing material, life time of beryllium and coated beryllium, dust and particle production, joining, waste treatment, mechanical properties and deformation by swelling were discussed as important issues. Especially, it was recognized throughout the discussions that the comparative study by the different researchers should be carried out to establish the reliability of the data reported in the workshop and in others. To enhance the comparative study, the world wide collaboration for the relative evaluation of the beryllium was proposed by the International Organization Committee and the proposal was approved by all of the participants. The 45 of the presented papers are indexed individually. (J.P.N.)

High heat flux tests on beryllium and beryllium-copper joints

International Nuclear Information System (INIS)

Roedig, M.; Duwe, R.; Linke, J.; Schuster, A.

1997-01-01

A large test program has been set up to evaluate the performance of beryllium as a plasma facing material for the divertor in thermonuclear fusion devices. Simulation of steady state heat loads of 5 MWm -2 and above on actively cooled divertor modules, and off-normal plasma conditions with energy densities in the range 1-7 MJm -2 , have been investigated. Thermal shock tests were carried out with the ITER reference grade S65-C and several Russian grades of beryllium. At incident energies up to 7 MJm -2 the best erosion behaviour is observed for S65-C and for TGP-56. Steady state heating tests with actively cooled Be/Cu mock-ups were performed at incident powers of up to 5.8 MWm -2 . All samples investigated in these tests did not show any indications of failure. A Be/Cu mock-ups with Incusil braze was loaded in thermal fatigue up to 500 cycles at an incident power of 4.8 MWm -2 . Up to the end of the experiment no temperature increase of the surface and no indication of failure was observed. (orig.)

Prehistory of Z=88 radium

International Nuclear Information System (INIS)

Schwankner, R.J.; Schoeffl, P.; Lieckfeld, G.

1994-01-01

Radium discovery in tailings of early uranium industry was the beginning of its widespread use e.g. in research, medicine and luminous paint production. It is this development taking place in various fields as well as recent results of custodian radiometry, that will be subject of the presentation. (orig.) [de

Retention of radium from thermal waters on sand filters and adsorbents

Energy Technology Data Exchange (ETDEWEB)

Elejalde, C. [Dpto. de Ingenieria Nuclear y Mecanica de Fluidos, Escuela Tecnica Superior de Ingenieria, Alameda de Urquijo s/n, 48013 Bilbao (Spain)]. E-mail: inpelsac@bi.ehu.es; Herranz, M. [Dpto. de Ingenieria Nuclear y Mecanica de Fluidos, Escuela Tecnica Superior de Ingenieria, Alameda de Urquijo s/n, 48013 Bilbao (Spain); Idoeta, R. [Dpto. de Ingenieria Nuclear y Mecanica de Fluidos, Escuela Tecnica Superior de Ingenieria, Alameda de Urquijo s/n, 48013 Bilbao (Spain); Legarda, F. [Dpto. de Ingenieria Nuclear y Mecanica de Fluidos, Escuela Tecnica Superior de Ingenieria, Alameda de Urquijo s/n, 48013 Bilbao (Spain); Romero, F. [Dpto. de Ingenieria Quimica y del Medio Ambiente, Escuela Tecnica Superior de Ingenieria, Alameda de Urquijo s/n, 48013 Bilbao (Spain); Baeza, A. [Dpto. de Fisica, Facultad de Veterinaria, Universidad de Extremadura, Avda. Universidad s/n, 10071 Caceres (Spain)

2007-06-18

This study was focussed on laboratory experiences of retention of radium from one thermal water on sand filters and adsorbents, trying to find an easy method for the elimination in drinkable waters polluted with this natural radio-nuclide. A thermal water from Cantabria (Spain) was selected for this work. Retention experiences were made with columns of 35 mm of diameter containing 15 cm layers of washed river sand or 4 cm layers of zeolite A3, passing known volumes of thermal water at flows between 4 and 40 ml/min with control of the retained radium by determining the amount in the water after the treatment. The statistical analysis of data suggests that retention depends on the flow and the volume passed through the columns. As additional adsorbents were used kaolin and a clay rich in illite. Jar-test experiences were made agitating known weights of adsorbents with the selected thermal water, with addition of flocculants and determination of radium in filtrated water after the treatment. Data suggest that retention is related to the weight of adsorbent used, but important quantities of radium seem remain in solution for higher amounts of adsorbents, according to the statistical treatment of data. The elution of retained radium from columns or adsorbents, previously used in experiences, should be the aim of a future research.

Retention of radium from thermal waters on sand filters and adsorbents

International Nuclear Information System (INIS)

Elejalde, C.; Herranz, M.; Idoeta, R.; Legarda, F.; Romero, F.; Baeza, A.

2007-01-01

This study was focussed on laboratory experiences of retention of radium from one thermal water on sand filters and adsorbents, trying to find an easy method for the elimination in drinkable waters polluted with this natural radio-nuclide. A thermal water from Cantabria (Spain) was selected for this work. Retention experiences were made with columns of 35 mm of diameter containing 15 cm layers of washed river sand or 4 cm layers of zeolite A3, passing known volumes of thermal water at flows between 4 and 40 ml/min with control of the retained radium by determining the amount in the water after the treatment. The statistical analysis of data suggests that retention depends on the flow and the volume passed through the columns. As additional adsorbents were used kaolin and a clay rich in illite. Jar-test experiences were made agitating known weights of adsorbents with the selected thermal water, with addition of flocculants and determination of radium in filtrated water after the treatment. Data suggest that retention is related to the weight of adsorbent used, but important quantities of radium seem remain in solution for higher amounts of adsorbents, according to the statistical treatment of data. The elution of retained radium from columns or adsorbents, previously used in experiences, should be the aim of a future research

Method of beryllium implantation in germanium substrate

International Nuclear Information System (INIS)

Kagawa, S.; Baba, Y.; Kaneda, T.; Shirai, T.

1983-01-01

A semiconductor device is disclosed, as well as a method for manufacturing it in which ions of beryllium are implanted into a germanium substrate to form a layer containing p-type impurity material. There after the substrate is heated at a temperature in the range of 400 0 C. to 700 0 C. to diffuse the beryllium ions into the substrate so that the concentration of beryllium at the surface of the impurity layer is in the order of 10 17 cm- 3 or more. In one embodiment, a p-type channel stopper is formed locally in a p-type germanium substrate and an n-type active layer is formed in a region surrounded by, and isolated from, the channel stopper region. In another embodiment, a relatively shallow p-type active layer is formed at one part of an n-type germanium substrate and p-type guard ring regions are formed surrounding, and partly overlapping said p-type active layer. In a further embodiment, a p-type island region is formed at one part of an n-type germanium substrate, and an n-type region is formed within said p-type region. In these embodiments, the p-type channel stopper region, p-type guard ring regions and the p-type island region are all formed by implanting ions of beryllium into the germanium substrate

TEM study of impurity segregations in beryllium pebbles

Energy Technology Data Exchange (ETDEWEB)

Klimenkov, M., E-mail: michael.klimenkov@kit.edu [Institute for Applied Materials – Applied Materials Physics, Karlsruhe Institute of Technology, Hermann-von-Helmholz-Platz 1, 76344 Eggenstein-Leopoldshafen (Germany); Chakin, V.; Moeslang, A. [Institute for Applied Materials – Applied Materials Physics, Karlsruhe Institute of Technology, Hermann-von-Helmholz-Platz 1, 76344 Eggenstein-Leopoldshafen (Germany); Rolli, R. [Institute for Applied Materials – Materials and Biomechanics, Karlsruhe Institute of Technology, Hermann-von-Helmholtz-Platz 1, 76344 Eggenstein-Leopoldshafen (Germany)

2014-12-15

Beryllium is planned to be used as a neutron multiplier in the Helium-cooled Pebble Bed European concept of a breeding blanket of demonstration power reactor DEMO. In order to evaluate the irradiation performance, individual pebbles and constrained pebble beds were neutron-irradiated at temperatures typical of fusion blankets. Beryllium pebbles 1 mm in diameter produced by the rotating electrode method were subjected to a TEM study before and after irradiation at High Flux Reactor, Petten, Netherlands at 861 K. The grain size varied in a wide range from sub-micron size up to several tens of micrometers, which indicated formation bimodal grain size distribution. Based on the application of combined electron energy loss spectroscopy and energy dispersive X-ray spectroscopy methods, we suggest that impurity precipitates play an important role in controlling the mechanical properties of beryllium. The impurity elements were present in beryllium at a sub-percent concentration form beryllide particles of a complex (Fe/Al/Mn/Cr)B composition. These particles are often ordered along dislocations lines, forming several micron-long chains. It can be suggested that fracture surfaces often extended along these chains in irradiated material.

State of uranium and radium radionuclides in the soil medium

International Nuclear Information System (INIS)

Vojnikova, E.V.; Sokolik, G.A.; Ovsyannikova, S.V.; Popenya, M.V.

2010-01-01

The reserves of migratory active, potentially mobile and potentially biologically available forms of uranium and radium in the mineral and organic soils of Belarus have been established. The uranium and radium species in the soil pore waters have been also studied. The received data makes possible the estimation of the radionuclide ability to participate in the processes of biogeochemical migration in terrestrial ecosystems. (authors)

Recent cases of radium-induced malignancy

International Nuclear Information System (INIS)

Adams, E.E.

1984-01-01

Three cases of malignant disease attributed to radium in patients with measured body burdens have been observed since 1978 - one paranasal sinus carcinoma, one mastoid carcinoma, and one fibrosarcoma of bone. These cases are summarized here. 4 references

Radium therapy for carcinoma of the tongue

International Nuclear Information System (INIS)

Matsuura, Shizumi; Makino, Sohtaro; Satake, Bunsuke; Takahashi, Keiichi; Sakaino, Kohji; Nakajima, Nobuaki

1984-01-01

Results of radium therapy with or without multi-disciplinary treatment for carcinoma of the tongue were studied in 117 patients treated from 1973 to 1981 at Gunma Cancer Center. 1. The patients were classified according to the TNM classification of UICC (1978). Seventeen patients were T1, 42 were T2, 31 were T3, 27 were T4, 92 were NO, 18 were N1, 2 were N2 and 5 were N3. 2. The treatment methods included external irradiation with 1,000-2,000 rads by 6MV X-ray followed by radium interstitial implants of 6,000-8,000 rads in 93 patients (73.9 per cent), radium therapy with additional Bleomycin 45-60 mg in 24 patients (20.5 per cent), and cryosurgery in 3 patients. 3. The five year survival rate was 41.6 per cent; 100.0 per cent for T1, 50.0 per cent for T2, 38.8 per cent for T3 and 10.5 per cent for T4. The overall five-year cumulative survival rate was 46.9 per cent. For primary lesions of T3 or T4, greater efforts should be made with combined modalities, such as planned multi-disciplinary treatments with combined radiation and major surgery. (author)

Co-precipitation of radium with barium and strontium sulfate and its impact on the fate of radium during treatment of produced water from unconventional gas extraction.

Science.gov (United States)

Zhang, Tieyuan; Gregory, Kelvin; Hammack, Richard W; Vidic, Radisav D

2014-04-15

Radium occurs in flowback and produced waters from hydraulic fracturing for unconventional gas extraction along with high concentrations of barium and strontium and elevated salinity. Radium is often removed from this wastewater by co-precipitation with barium or other alkaline earth metals. The distribution equation for Ra in the precipitate is derived from the equilibrium of the lattice replacement reaction (inclusion) between the Ra(2+) ion and the carrier ions (e.g., Ba(2+) and Sr(2+)) in aqueous and solid phases and is often applied to describe the fate of radium in these systems. Although the theoretical distribution coefficient for Ra-SrSO4 (Kd = 237) is much larger than that for Ra-BaSO4 (Kd = 1.54), previous studies have focused on Ra-BaSO4 equilibrium. This study evaluates the equilibria and kinetics of co-precipitation reactions in Ra-Ba-SO4 and Ra-Sr-SO4 binary systems and the Ra-Ba-Sr-SO4 ternary system under varying ionic strength (IS) conditions that are representative of brines generated during unconventional gas extraction. Results show that radium removal generally follows the theoretical distribution law in binary systems and is enhanced in the Ra-Ba-SO4 system and restrained in the Ra-Sr-SO4 system by high IS. However, the experimental distribution coefficient (Kd') varies widely and cannot be accurately described by the distribution equation, which depends on IS, kinetics of carrier precipitation and does not account for radium removal by adsorption. Radium removal in the ternary system is controlled by the co-precipitation of Ra-Ba-SO4, which is attributed to the rapid BaSO4 nucleation rate and closer ionic radii of Ra(2+) with Ba(2+) than with Sr(2+). Carrier (i.e., barite) recycling during water treatment was shown to be effective in enhancing radium removal even after co-precipitation was completed. Calculations based on experimental results show that Ra levels in the precipitate generated in centralized waste treatment facilities far

The development of beryllium plasma spray technology for the International Thermonuclear Experimental Reactor (ITER)

International Nuclear Information System (INIS)

Castro, R.G.; Elliott, K.E.; Hollis, K.J.; Watson, R.D.

1999-01-01

Over the past five years, four international parties, which include the European Communities, Japan, the Russian Federation and the United States, have been collaborating on the design and development of the International Thermonuclear Experimental Reactor (ITER), the next generation magnetic fusion energy device. During the ITER Engineering Design Activity (EDA), beryllium plasma spray technology was investigated by Los Alamos National Laboratory as a method for fabricating and repairing and the beryllium first wall surface of the ITER tokamak. Significant progress has been made in developing beryllium plasma spraying technology for this application. Information will be presented on the research performed to improve the thermal properties of plasma sprayed beryllium coatings and a method that was developed for cleaning and preparing the surface of beryllium prior to depositing plasma sprayed beryllium coatings. Results of high heat flux testing of the beryllium coatings using electron beam simulated ITER conditions will also be presented

SPECTROGRAPHIC DETERMINATION OF BERYLLIUM IN OILFIELD WATERS USING A PLASMA ARC

Energy Technology Data Exchange (ETDEWEB)

Collins, A. G.; Pearson, C. A.

1963-10-15

Geochemical studies of the distribution of the trace, minor, and major constituents of oilfield waters aid in the exploration for petroleum and other minerals, determination of the origin and distribution of oilfield waters and petroleum, and location of casing leaks and of water pollution sources. The determination of the beryllium and related data should be useful in these studies. An emission spectrographic method utilizing a plasma arc assembly for determining beryllium in oilfield waters, with a sensitivity permitting detection of less than 1 ppb, was developed. Beryllium was extracted from synthetic and natural oilfield waters with chloroform and acetylacetone. The extracts were aspirated directly into the plasma arc, and the beryllium emission intensity was recorded on photographic plates. (auth)

Reactivity effect of poisoned beryllium block shuffling in the MARIA reactor

International Nuclear Information System (INIS)

Andrzejewski, K.; Kulikowska, T.

2000-01-01

The paper is a continuation of the analysis of beryllium blocks poisoning by Li-6 and He-3 in the MARIA reactor, presented at the 22 RERTR Meeting in Budapest. A new computational tool, the REBUS-3 code, has been used for predicting the amount of poison. The code has been put into operation on a HP computer and the beryllium transmutation chains have been activated with assistance of the ANL RERTR staff. The horizontal and vertical poison distribution within beryllium blocks has been studied. A simple shuffling of beryllium blocks has been simulated to check the effect of exchanging a block with high poison concentration, adjacent to fuel elements, with a peripheral one with a low poison concentration

Development and experimental study of beryllium window for ITER radial X-ray camera

Energy Technology Data Exchange (ETDEWEB)

Chen, Zhaoxi [Institute of Plasma Physics, Chinese Academy of Sciences, Hefei 230031 (China); Jin, Guangxu [Materion Brush (United States); Chen, Kaiyun; Chen, Yebin; Song, Yuntao [Institute of Plasma Physics, Chinese Academy of Sciences, Hefei 230031 (China); Hu, Liqun, E-mail: lqhu@ipp.ac.cn [Institute of Plasma Physics, Chinese Academy of Sciences, Hefei 230031 (China); Niu, Luying; Sheng, Xiuli; Cheng, Yong; Lu, Kun [Institute of Plasma Physics, Chinese Academy of Sciences, Hefei 230031 (China)

2013-12-15

Highlights: • The thickness of the beryllium foil is chosen as 80 μm to guarantee its safety under high pressure differential in accident events. • Using low purity of beryllium as the transition material, the effect of thermal stress caused by diffusion bonding process can be reduced. • Sealing ring and honeycomb-like supports are designed and used in the mechanical clamped beryllium window to enhance its sealing and safety performance. • The beryllium windows have good performance under severe working conditions like high temperature baking, vibration or impact load. -- Abstract: Radial X-ray camera (RXC) is a diagnostic device planned to be installed in the ITER Equatorial Port no. 12. Beryllium window will be installed between the inner and outer camera of RXC, which severs as the transmission photocathode substrate and also the vacuum isolation component. In this paper the design and manufacture process of two types of beryllium windows were introduced. Although 50 μm thickness of beryllium foil is the best choice, the 80 μm one with X-ray threshold of 1.34 keV was selected for safety consideration. Using the intermediate layer (low purity of beryllium) between the beryllium foil and the stainless steel base flange is an effective strategy to limit the welding thermal deformation and thermal stress of the thin foil caused by bonding between different materials. By using ANSYS software, the feasibility of the aperture design was analyzed and validated. Metal sealing ring was applied in the mechanical clamped beryllium window for its good stability under high temperature and neutron radiation. Although both of the hollow metal sealing ring with 0.03 mm silver coating and the pure silver sealing ring can satisfy the sealing requirement, the later one was chosen to produce the final product. Two hours 240 °C high temperature baking test, two hours 3.3 Hz vibration test and fatigue test were performed on the two types of beryllium windows. Based on the

SOURCE AND PATHWAY DETERMINATION FOR BERYLLIUM FOUND IN BECHTEL NEVADA NORTH LAS VEGAS FACILITIES

Energy Technology Data Exchange (ETDEWEB)

BECHTEL NEVADA

2004-07-01

In response to the report ''Investigation of Beryllium Exposure Cases Discovered at the North Las Vegas Facility of the National Nuclear Security Administration'', published by the U.S. Department of Energy (DOE), National Nuclear Security Administration (NNSA) in August 2003, Bechtel Nevada (BN) President and General Manager Dr. F. A. Tarantino appointed the Beryllium Investigation & Assessment Team (BIAT) to identify both the source and pathway for the beryllium found in the North Las Vegas (NLV) B-Complex. From September 8 to December 18, 2003, the BIAT investigated the pathway for beryllium and determined that a number of locations existed at the Nevada Test Site (NTS) which could have contained sufficient quantities of beryllium to result in contamination if transported. Operations performed in the B-1 Building as a result of characterization activities at the Engine Maintenance, Assembly, and Disassembly (EMAD); Reactor Maintenance, Assembly, and Disassembly (RMAD); Test Cells A and C; and the Central Support Facility in Area 25 had the greatest opportunity for transport of beryllium. Investigative monitoring and sampling was performed at these sites with subsequent transport of sample materials, equipment, and personnel from the NTS to the B-1 Building. The timeline established by the BIAT for potential transport of the beryllium contamination into the B-1 Building was from September 1997 through November 2002. Based on results of recently completed swipe sampling, no evidence of transport of beryllium from test areas has been confirmed. Results less than the DOE beryllium action level of 0.2 ???g/100 cm2 were noted for work support facilities located in Area 25. All of the identified sites in Area 25 worked within the B-1 tenant's residency timeline have been remediated. Legacy contaminants have either been disposed of or capped with clean borrow material. As such, no current opportunity exists for release or spread of beryllium

Myeloid leukaemia/osteosarcoma ratio in CBA/H mice given radium 224

International Nuclear Information System (INIS)

Humphreys, E.R.; Stones, V.A.

1989-01-01

Four groups of 400 12-week-old CBA/H mice were injected intraperitoneally with mean amounts of 69, 139, 280 and 550 Bq/g -1 radium 224. A further group of 400 mice were injected intraperitoneally with diluting solution only. The mice were allowed unrestricted access to food and water until they died or were killed. To date (September 1988) about 40% of the mice are dead, and 28 cases of myeloid leukaemia and four cases of osteosarcoma have been diagnosed in the animals given radium 224. The relationship between the yield of myeloid leukaemia and the amount of radium 224 injected was found to be curvilinear. The determined value of the myeloid leukaemia:osteosarcoma ratio is discussed. (author)

Method of crude ore defluoridation in hydrometallurgy of beryllium, affording fluorosilicic acid

International Nuclear Information System (INIS)

Samojlov, V.I.; Borsuk, A.N.; Zherin, I.I.

2006-01-01

Results of laboratory and industrial tests conducted at Ul'ba Metallurgical Plant on leaching bertrandite - phenacite - fluorite flotation concentrate containing ∼4 wt. % beryllium in a rotary furnace using sulfuric acid are presented. The technology is shown to provide a 7.8% reduction in the net cost of beryllium production (1 kg) in the form of technical-grade Be(OH) 2 by obviating the need of smelting beryllium concentrates and alkali fluxes. Besides, the technology permits concomitant production of H 2 SiF 6 , its commercial sales promoting a 17.6% reduction in beryllium production net cost [ru

Thermal Properties of Beryllium Metal

International Nuclear Information System (INIS)

Cho, Tae Won; Baek, Je Kyun; Jeong, Gwan Yoon; Kim, Ji Hyeon; Sohn, Dong Seong

2013-01-01

It is known that the presence of as-fabricated porosity largely affect thermal conductivity of beryllium. Therefore, in this paper we will suggest a new thermal conductivity equation which consider volume fraction and discuss how this can be applied to irradiation induced degradation of thermal conductivity later. This study was performed to develop a new correlation of thermal conductivity of Beryllium. Although there are many factors like BeO contents, impurity level, grain size, and porosity, we assumed porosity will be the dominant factor for thermal conductivity. Therefore, a new correlation which consider volume fraction by applying Maxwell-Eucken equation is developed and this is consistent to some degrees. However, increasing impurity level and decreasing grain size will decrease thermal conductivity. Therefore, we need to consider their effects although we assume BeO contents, impurity, and grain size do not make noticeable effects in the future. Furthermore, thermal conductivity degradation by neutron irradiation should be considered afterward. There are two main factors for the thermal conductivity degradation: the one is defects formed by neutron collisions and the other is helium generated by transmutation of Be. It is known that they make a considerable degradation of conductivity. Beryllium is known there are considerable volume increases by helium accumulation. Therefore, we anticipate our suggested model can be applicable if it has been developed furthermore considering irradiation induced swelling

Analysis of the KANT experiment on beryllium using TRIPOLI-4 Monte Carlo code

International Nuclear Information System (INIS)

Lee, Yi-Kang

2011-01-01

Beryllium is an important material in fusion technology for multiplying neutrons in blankets. However, beryllium nuclear data are differently presented in modern nuclear data evaluations. Recent investigations with the TRIPOLI-4 Monte Carlo simulation of the tritium breeding ratio (TBR) demonstrated that beryllium reaction data are the main source of the calculation uncertainties between ENDF/B-VII.0 and JEFF-3.1. To clarify the calculation uncertainties from data libraries on beryllium, in this study TRIPOLI-4 calculations of the Karlsruhe Neutron Transmission (KANT) experiment have been performed by using ENDF/B-VII.0 and new JEFF-3.1.1 data libraries. The KANT Experiment on beryllium has been used to validate neutron transport codes and nuclear data libraries. An elaborated KANT experiment benchmark has been compiled and published in the NEA/SINBAD database and it has been used as reference in the present work. The neutron multiplication in bulk beryllium assemblies was considered with a central D-T neutron source. Neutron leakage spectra through the 5, 10, and 17 cm thick spherical beryllium shells were calculated and five-group partial leakage multiplications were reported and discussed. In general, improved C/E ratios on neutron leakage multiplications have been obtained. Both ENDF/B-VII.0 and JEFF-3.1.1 beryllium data libraries of TRIPOLI-4 are acceptable now for fusion neutronics calculations.

HEINBE; the calculation program for helium production in beryllium under neutron irradiation

International Nuclear Information System (INIS)

Shimakawa, Satoshi; Ishitsuka, Etsuo; Sato, Minoru

1992-11-01

HEINBE is a program on personal computer for calculating helium production in beryllium under neutron irradiation. The program can also calculate the tritium production in beryllium. Considering many nuclear reactions and their multi-step reactions, helium and tritium productions in beryllium materials irradiated at fusion reactor or fission reactor may be calculated with high accuracy. The calculation method, user's manual, calculated examples and comparison with experimental data were described. This report also describes a neutronics simulation method to generate additional data on swelling of beryllium, 3,000-15,000 appm helium range, for end-of-life of the proposed design for fusion blanket of the ITER. The calculation results indicate that helium production for beryllium sample doped lithium by 50 days irradiation in the fission reactor, such as the JMTR, could be achieved to 2,000-8,000 appm. (author)

Behavior of beryllium pebbles under irradiation

Energy Technology Data Exchange (ETDEWEB)

Dalle-Donne, M.; Scaffidi-Argentina, F. [Forschungszentrum Karlsruhe GmbH Technik und Umwelt (Germany). Inst. fuer Neutronenphysik und Reactortechnik; Baldwin, D.L.; Gelles, D.S.; Greenwood, L.R.; Kawamura, H.; Oliver, B.M.

1998-01-01

Beryllium pebbles are being considered in fusion reactor blanket designs as neutron multiplier. An example is the European `Helium Cooled Pebble Bed Blanket.` Several forms of beryllium pebbles are commercially available but little is known about these forms in response to fast neutron irradiation. Commercially available beryllium pebbles have been irradiated to approximately 1.3 x 10{sup 22} n/cm{sup 2} (E>1 MeV) at 390degC. Pebbles 1-mm in diameter manufactured by Brush Wellman, USA and by Nippon Gaishi Company, Japan, and 3-mm pebbles manufactured by Brush Wellman were included. All were irradiated in the below-core area of the Experimental Breeder Reactor-II in Idaho Falls, USA, in molybdenum alloy capsules containing helium. Post-irradiation results are presented on density change measurements, tritium release by assay, stepped-temperature anneal, and thermal ramp desorption tests, and helium release by assay and stepped-temperature anneal measurements, for Be pebbles from two manufacturing methods, and with two specimen diameters. The experimental results on density change and tritium and helium release are compared with the predictions of the code ANFIBE. (author)

Hydrogeology of the Dakota Group aquifer with emphasis on the radium-226 content of its contained ground water, Canon City Embayment, Fremont and Pueblo Counties, Colorado

International Nuclear Information System (INIS)

Vinckier, T.A.

1982-01-01

The Dakota Group aquifer of the Canon City embayment comprises two primary water-bearing units, the Lytle Sandstone Member at the base and the Dakota Sandstone at the top, separated by the semiconfining, arenaceous Glencairn Shale Member. The ground water in this area probably represents a mixture of some or all of the following genetic types: (1) ground water connate to the Dakota Group; (2) ground water, connate or otherwise, entering the aquifer as leakage from adjacent semiconfining strata; (3) deeply circulated meteoric ground water; and (4) hydrothermal fluids (magmatic or metamorphic ground water) purged from the crystalline basement complex underlying the embayment. The contents of the radium-226 in ground water from 117 wells completed in part or all of the Dakota Group were determined by the dissolved radon-222 emanation method. Sixty-seven percent of the ground water samples have radium-226 activities greater than 5.0 picocuries per liter of water (5.0 pCi/1), the recommended maximum permissible concentration of radium-226 in drinking water established by the Environmental Protection Agency in 1973. Inspection of gamma-ray logs of about 20 wells revealed the presence of moderate to extremely high gamma radiation in strata of the Dakota Group, the Morrison Formation, the Fountain Formation, and in the crystalline basement rocks. High levels of radium-226 in drinking water supplies pose potentially serious health hazards to the users. Owners of wells producing such water supplies are advised to (1) install, at the homesite, ion exchange (filtering units) capable of removing 226 Ra 2 + ions and other aqueous radium species from the water or (2) effectively case out those stratigraphic intervals in the bore hole showing high gamma radiation preventing possible radium-rich ground water within these intervals from entering the well

Uranium and radium in Finnsjoen - an experimental approach for calculation of transfer factors

International Nuclear Information System (INIS)

Evans, S.; Bergman, R.

1981-01-01

The radiological safety studies for underground disposal of HLW show that the future individual and collective doses to an important extent may originate from groundwater borne radium and uranium which reach the biosphere. Indications that the dispersion rates presently used give rise to overestimations of calculated doses justified an investigation for more realistic turnover rates of radium and uranium than those which now are in use. Within one of the sites selected for testing, the area around lake Finnsjoen, a small number of environmental samples were collected and analyzed with respect to radium and uranium and the new transfer coefficients between soil and lake water were derived. The dose rates obtained with the new transfer factors show a close agreement for radium and a slight increase for uranium compared with earlier calculations. (Auth.)

New and Emerging Technologies for Real-Time Air and Surface Beryllium Monitoring

Energy Technology Data Exchange (ETDEWEB)

Phifer, B.E. Jr.; Churnetski, E.L.; Cooke, L.E.; Reed, J.J.; Howell, M.L.; Smith, V.D.

2001-09-01

In this study, five emerging technologies were identified for real-time monitoring of airborne beryllium: Microwave-Induced Plasma Spectroscopy (MIPS), Aerosol Beam-Focused Laser-Induced Plasma Spectroscopy (ABFLIPS), Laser-Induced Breakdown Spectroscopy (LIBS), Surfaced-Enhanced Raman Scattering (SERS) Spectroscopy, and Micro-Calorimetric Spectroscopy (CalSpec). Desired features of real-time air beryllium monitoring instrumentation were developed from the Y-12 CBDPP. These features were used as guidelines for the identification of potential technologies as well as their unique demonstrated capability to provide real-time monitoring of similar materials. However, best available technologies were considered, regardless of their ability to comply with the desired features. None of the five technologies have the capability to measure the particle size of airborne beryllium. Although reducing the total concentration of airborne beryllium is important, current literature suggests that reducing or eliminating the concentration of respirable beryllium is critical for worker health protection. Eight emerging technologies were identified for surface monitoring of beryllium. CalSpec, MIPS, SERS, LIBS, Laser Ablation, Absorptive Stripping Voltametry (ASV), Modified Inductively Coupled Plasma (ICP) Spectroscopy, and Gamma BeAST. Desired features of real-time surface beryllium monitoring were developed from the Y-12 CBDPP. These features were used as guidelines for the identification of potential technologies. However, the best available technologies were considered regardless of their ability to comply with the desired features.

Encapsulation, shielding, and packaging for conditioning of spent radium sources

International Nuclear Information System (INIS)

Kang, I. S.; Kim, T. K.; Lee, B. C.; Kim, G. J.; Hong, K. P.

2002-01-01

The appropriate management and conditioning of spent radium sources have been risen to one of the greatest challenges faced by the international society. The expert teams in Korea were organized to tackle this problem by the request of IAEA and supported to condition sources in Southeastern Asia. The main object of this paper is to apply safely and effectively conditioning of spent sealed sources in our country near future by virtue of describing the technology on conditioning the national inventory of spent radium sources in Singapore. The paper is the result that the Korean expert team successfully carried out the conditioning of spent radium sources in Singapore with accumulated experiences. The conditioning operation was carried out under the supervision of IAEA's technical officer, Mr. Al-Mughrabi and Singapore Nuclear Cancer Centre. The 204 sources of spent radium stored in Singapore were encapsuled and welded in 17 small capsules and a large capsule, and conditioned in 2 lead shields, producing 2 package. As a result of this operation, a total amount of 938.56mg were conditioned and distributed into 2 shielding devices, holding 497.5mg and 441.06mg. In addition, the contaminated objects and the secondary wastes produced during segregation and dismantling of sources were immobilized in a plastic box

Retrospective beryllium exposure assessment at the Rocky Flats Environmental Technology site

International Nuclear Information System (INIS)

Barnard, A.E.; Torma-Krajewski, J.; Viet, S.M.

1997-01-01

Since the 1960's, beryllium machining was performed to make nuclear weapon components at the Department of Energy (DOE) Rocky Flats Plant. Beryllium exposure was assessed via fixed airhead (FAH) sampling in which the filter cassette was affixed to the machine, generally within a few feet of the worker's breathing zone. Approximately 500,000 FAH samples were collected for beryllium over three decades. From 1984 to 1987, personal breathing zone (PBZ) samples were also collected as part of the evaluation of a new high velocity/low volume local exhaust ventilation (HV/LV LEV) system. The purpose of this study was to determine how the two types of sampling data could be used for an exposure assessment in the beryllium shop

Neutron induced displacement damage in beryllium in the blanket of a (d,t)-fusion reactor

International Nuclear Information System (INIS)

Hermanutz, D.

1995-09-01

Beryllium is a favoured candidate for a neutron multiplier in solid breeder blankets of fusion reactors. This is mainly due to its low (n, 2n)-reaction threshold and because of its good thermal and mechanical properties. Its behaviour under intense neutron irradiation, however, is a crucial issue for its use in future fusion reactors. Displacement damage in beryllium so far has been calculated both with data related and methodological deficiencies. First of all, there is a need to have accurate cross-section data in order to obtain reliable spectra of primary knock-on atoms (PKA's). Furthermore, there are principal restrictions of the NRT-model in general used to calculate secondary displacements initiated by PKA's. The underlying theory of damage-energy (part of kinetic energy of PKA transferred elastically to matrix atoms) according to Lindhard is strictly valid only for medium and heavy mass ions with moderate energies in targets of the same element. In this work improved damage cross-sections and displacement rates (dpa/s) in beryllium have been calculated based on cross-section data from ENDF/B-VI (with a significantly improved (n, 2n)-evaluation) and on an appropriate treatment of damage-energy that is suitable for fusion relevant damage of light mass materials. ''This work has been performed in the framework of the Nuclear Fusion Project of the Forschungszentrum Karlsruhe and is supported by the European Communities within the European Fusion Technology Program''. (orig.)

JET-ISX-B beryllium limiter experiment safety analysis report and operational safety requirements

International Nuclear Information System (INIS)

Edmonds, P.H.

1985-09-01

An experiment to evaluate the suitability of beryllium as a limiter material has been completed on the ISX-B tokamak. The experiment consisted of two phases: (1) the initial operation and characterization in the ISX experiment, and a period of continued operation to the specified surface fluence (10 22 atoms/cm 2 ) of hydrogen ions; and (2) the disassembly, decontamination, or disposal of the ISX facility. During these two phases of the project, the possibility existed for beryllium and/or beryllium oxide powder to be produced inside the vacuum vessel. Beryllium dust is a highly toxic material, and extensive precautions are required to prevent the release of the beryllium into the experimental work area and to prevent the contamination of personnel working on the device. Details of the health hazards associated with beryllium and the appropriate precautions are presented. Also described in appendixes to this report are the various operational safety requirements for the project

Campaign to gather medical devices containing radium: results

International Nuclear Information System (INIS)

Pierre, J.P.; Vidal, J.P.; Martin, J.C.; Pasquier, J.L.

2002-01-01

Campaign to gather medical devices containing radium: results. On December 1, 1999, at the request of the French Health Ministry, OPRI and ANDRA launched a campaign to gather medical devices containing radium, formerly used in brachytherapy. This campaign addressed a public health issue because of the risks actually involved in a careless handling of these objects. Moreover the growing number of reported scattered radium medical devices in the last few years reinforced the necessity of the campaign. The gathering was initiated by a call of the owners (hospitals, caring centers, retired doctors or their heirs) to a toll free number. OPRI or ANDRA then appreciated the situation urgency. Priority was given to private people because most of them did not have suitable storage facilities. OPRI teams operated according a strict protocol guaranteeing their own safety, proper procedures and compliance with transport regulations for radioactive materials. 517 objects amounting to an activity of 1.32 x 10 11 Bq have been gathered in 90 operations. Properly packaged they were transported to and safely stored at the CEA Saclay site before their permanent storage in the ANDRA facilities. (author)

Distribution of radium and plutonium in human bone

International Nuclear Information System (INIS)

Schlenker, R.A.

1985-01-01

This review covers studies of the microdistribution of radium and plutonium in human bone, conducted at Argonne with emphasis on the alpha-spectrometric method of measurement. Alpha spectrometry offers high spatial resolution and is well suited to the measurement of radionuclide concentrations near bone surfaces. With these techniques surface deposit thicknesses have been measured to be about 1 μm thick for isotopes of lead, radium and the actinides, and volume deposits of 226 Ra have been found to be quite nonuniform near bone surfaces, leading to endosteal tissue dose rates that are higher than expected under the assumption of uniform volume concentration normally used in radiation protection calculations. With autoradiography, the bony septa of the mastoid air cell system have been found to be depleted in radium relative to the bone tissue surrounding them; this is expected to have a significant influence on the dosimetry of the mastoid epithelia. A combination of autoradiographic and morphometric measurements indicates that specific activities in the axial skeleton are higher than in the appendicular skeleton, primarily because the former has higher bone surface-to-volume ratios and higher bone surface concentrations of plutonium. 19 references, 14 figures, 6 tables

Radium removal for a small community water-supply system. Research report, 1 October 1985-30 September 1987

International Nuclear Information System (INIS)

Mangelson, K.A.

1988-07-01

In 1984, a radium-removal treatment plant was constructed for the small community of Redhill Forest located in the central mountains of Colorado. The treatment plant consists of a process for removing iron and manganese ahead of an ion-exchange process for the removal of radium. The raw water comes from deep wells and has naturally occurring radium and iron concentrations of about 30-40 pCi/L and 7-10 mg/L, respectively. Before the raw water enters the main treatment plant, the raw water is aerated to remove radon gas and carbon dioxide. The unique features of the Redhill Forest Treatment Plant are related to the ways in which the radium removed from the raw water is further treated and eventually disposed of as treatment plant waste. A separate system removes only radium from the backwash/regeneration water of the ion exchange process and the radium is permanently complexed on a Radium Selective Complexer (RSC) resin made by Dow Chemical. The RSC resin containing radium is replaced with virgin resin as needed and the resin waste transported to a permanent final disposal site in Beatty, NV. This report presents a detailed description of the Redhill Forest treatment system and the results of in-depth monitoring of the processes and other factors relating to the overall operation of the radium-removal system. Included are descriptions of modifications made in the plant operation to improve the overall system operation and of the procedures for final disposal of the RSC resin-containing radium

Neutron activation analysis: Modelling studies to improve the neutron flux of Americium–Beryllium source

Directory of Open Access Journals (Sweden)

Abdessamad Didi

2017-06-01

Full Text Available Americium–beryllium (Am-Be; n, γ is a neutron emitting source used in various research fields such as chemistry, physics, geology, archaeology, medicine, and environmental monitoring, as well as in the forensic sciences. It is a mobile source of neutron activity (20 Ci, yielding a small thermal neutron flux that is water moderated. The aim of this study is to develop a model to increase the neutron thermal flux of a source such as Am-Be. This study achieved multiple advantageous results: primarily, it will help us perform neutron activation analysis. Next, it will give us the opportunity to produce radio-elements with short half-lives. Am-Be single and multisource (5 sources experiments were performed within an irradiation facility with a paraffin moderator. The resulting models mainly increase the thermal neutron flux compared to the traditional method with water moderator.

Geological implications of radium and helium in oil-field brines: observations, inferences and speculations

International Nuclear Information System (INIS)

Lerche, I.

1993-01-01

The 1600 yr half-life of radium restricts the time and thus the distance over which radium can migrate in sediments. The dominant source of unsupported radium in sandstone reservoir brines must then be close by and is likely in shales adjacent to the oil-field reservoirs. The chemical similarity of calcium and radium can be used to argue for a local shale-source contribution to the calcium in reservoir sands -suggesting the probability of calcite cementation early in the sedimentary sequence. Helium production by radium decay increases with time. Concentrations of helium found in reservoir oil field brines are then used to suggest that: (a) such reservoirs are dominantly closed systems over geological times; (b) neither methane nor helium in the reservoirs have migrated any significant distance; and (c) the mechanism responsible for the observed helium in the brine is a continuous on-going process operative today. Diagenetic studies should then deal with both sands and shales interdependently, the two are not separable. Shales control the transport mechanisms of migration so that the primary migration of hydrocarbons, the result of kerogen catagenesis in shales, should occur sufficiently early in the sedimentary sequence in order to avoid exclusion from the reservoir by calcite cementation in association with radium transport. (author)

The fantastic history of radium: when a radioactive element becomes a magic potion; La fantastique histoire du radium: Quand un element radioactif devient potion magique

Energy Technology Data Exchange (ETDEWEB)

Cosset, Jean-Marc; Huynh, Renaud

2011-04-18

More than a century after its discovery, radium has never lost its symbolic power: the symbol of scientific perseverance with Marie Curie handling quintals of ore to extract this 'fabulous metal', symbol of radiations efficiency against cancer, symbol of eternity and value - like diamond, and many more. The power of such a symbol led some mercantile minds to make radium a panacea capable to cure any illness. Then between the first and the second World war, radium became a society phenomenon: popular book writers held of the magic name to imagine wild stories and the advertisers started to link it to any type of product (beverages, shoe polish, razor blades, cigarettes, cheese, condoms..). This book relates the story of this symbol over more than a century, with its successes, its excesses and sometimes its dramas. (J.S.)

Modeling tritium processes in plasma-facing beryllium

International Nuclear Information System (INIS)

Longhurst, G.R.; Anderl, R.A.; Dolan, T.J.; Mulock, M.J.

1995-01-01

In this paper we present techniques and recommended parameters for modeling tritium implantation, trapping and release, and permeation, in beryllium-clad structures adjacent to the plasma. Among the features that should be considered are the effects of surface films, the mobility of beryllium through those films, damage caused by ion implantation, especially in regions where pitting may be expected, and bubble formation. Tritium transport parameters recommended are based on fits with experimental data and available theory. Estimates of inventories in ITER using these parameters are also given. 31 refs., 2 figs., 1 tab

The status of beryllium research for fusion in the United States

International Nuclear Information System (INIS)

Longhurst, G.R.; Snead, L.L.; Abou-Sena, A.A.

2004-01-01

Use of beryllium in fusion reactor has been considered for neutron multiplication in breeding blankets an as an oxygen getter for plasma - facing surface. Previous beryllium research for fusion in the United States included issues of interest to fission (swelling an changes in mechanical and thermal properties) as well as interactions with plasmas and hydrogen isotopes and methods of fabrication. When the United States formally withdrew its participation in the International Experimental Reactor (ITER) program, much of this effort was terminated. The focus in the U.S. has been mainly on toxic effects of beryllium and on industrial hygiene and health-related issues. Work continued at the INEEL (Idaho National Engineering and Environmental Laboratory) and elsewhere on beryllium-containing molten salts. This activity is part of the JUPITER II Agreement. Plasma spray of ITER first wall samples at Los Alamos National Laboratory has been performed under the European Fusion Development Agreement. Effects of irradiation on beryllium structure are being studied at Oak Ridge National Laboratory. Numerical and phenomenological models are being developed and applied at the University of California Los Angels to investigate thermo-mechanical characteristics of beryllium pebble beds, similar to research being carried out at Forschungszentrum Karlsruhe and elsewhere. Additional work, not funded by the fusion program, has dealt with issues of disposal, and recycling. (author)

The Status of Beryllium Research for Fusion in the United States

International Nuclear Information System (INIS)

Glen R. Longhurst

2003-01-01

Use of beryllium in fusion reactors has been considered for neutron multiplication in breeding blankets and as an oxygen getter for plasma-facing surfaces. Previous beryllium research for fusion in the United States included issues of interest to fission (swelling and changes in mechanical and thermal properties) as well as interactions with plasmas and hydrogen isotopes and methods of fabrication. When the United States formally withdrew its participation in the International Thermonuclear Experimental Reactor (ITER) program, much of this effort was terminated. The focus in the U.S. has been mainly on toxic effects of beryllium and on industrial hygiene and health-related issues. Work continued at the INEEL and elsewhere on beryllium-containing molten salts. This activity is part of the JUPITER II Agreement. Plasma spray of ITER first wall samples at Los Alamos National Laboratory has been performed under the European Fusion Development Agreement. Effects of irradiation on beryllium structure are being studied at Oak Ridge National Laboratory. Numerical and phenomenological models are being developed and applied to better understand important processes and to assist with design. Presently, studies are underway at the University of California Los Angeles to investigate thermo-mechanical characteristics of beryllium pebble beds, similar to research being carried out at Forschungszentrum Karlsruhe and elsewhere. Additional work, not funded by the fusion program, has dealt with issues of disposal, and recycling

Fabrication and replacement work of beryllium frame and gamma-ray shield

International Nuclear Information System (INIS)

Watahiki, Shunsuke; Hanawa, Yoshio; Asano, Norikazu; Hiyama, Kazuhisa; Ito, Sachito; Tsuboi, Kazuaki; Fukasaku, Akitomi

2012-03-01

This replacement work was carried out under refurbishment plan of JMTR for beryllium distortion draw to acceptable limit. And gamma-ray shield refurbishment was carried out the view point of prevention maintenance in consideration of operation plan. Fabrication of beryllium frame and gamma-ray shield was spent for two years it was finished in February, 2010. It took five months to replacement work from January 2010. In this report is presented fabrication and replacement work of beryllium frame and gamma-ray shield. (author)

Design of semi industrial radium separator by a new bacterium MGF-48

International Nuclear Information System (INIS)

Ghafourian, H.; Emami, M.R.; Farazmand, A.

1998-01-01

Following of a research work which has been recently published in AEOI scientific Bulletin no. 14, a semi industrial bioreactor has been designed for separation of radium using a new bacterium MGF-48. This bioreactor could be utilized for a high rate separation of radium in semi industrial scale. (author)

Codeposition of deuterium ions with beryllium oxide at elevated temperatures

CERN Document Server

Markin, A V; Gorodetsky, A E; Negodaev, M A; Rozhanskii, N V; Scaffidi-Argentina, F; Werle, H; Wu, C H; Zalavutdinov, R K; Zakharov, A P

2000-01-01

Deuterium-loaded BeO films were produced by sputtering the beryllium target with 10 keV Ne ions in D sub 2 gas at a pressure of approximately 1 Pa. The sputtered beryllium reacts - on the substrate surface - with the residual oxygen, thus forming a beryllium oxide layer. Biasing the substrate negatively with respect to the target provides the simultaneous bombardment of the growing film surface with D ions formed by Ne-D sub 2 collisions. Substrate potential governs the maximum energy of ions striking the growing film surface while its size governs the flux density. According to X-ray photoelectron spectroscopy (XPS), electron probe microanalysis (EPMA) and reflection high energy electron diffraction (RHEED) data, the beryllium is deposited in the form of polycrystalline hcp-BeO layers with negligible (about 1 at.%) carbon and neon retention. Thermal desorption spectroscopy (TDS) data shows a strong deuterium bonding, with a desorption peak at 950 K, in the films deposited at -50 and -400 V substrate potentia...

Non-neoplastic calcified tissue pathologies among radium workers and plutonium injectees

International Nuclear Information System (INIS)

Stebbings, J.H.

1997-01-01

Two human studies of deterministic effects of radium and plutonium are summarized. Histopathology data from femurs of New Jersey radium workers demonstrate effects of radium at ∼0.8 Gy skeletal dose. Toxicity ratio data from beagles suggest equivalent histopathological effects from 239 Pu may occur in humans at skeletal doses of ∼0.12 Gy in compact bone or at ∼0.01-0.02 Gy in spongy bone. These results support observations that subjects injected with plutonium in the 1940s showed bone changes typical of alpha radiation exposures, extensive osteoporosis with related fractures, and hearing disorders or vertigo related to bone damage and/or middle ear inflammation, all findings suggested by the clinical radium literature. A probable case of extensive pathologic calcification from a plutonium injection also occurred. In two cases suspect findings occurred at skeletal doses of ∼0.05 Gy. It is hypothesized that subjects with collagen disorders and uremic insufficiencies, as well as females late in life, form subpopulations susceptible to non-stochastic effects of internal alpha-emitters. In general, bone fractures late in life secondary to osteoporosis are associated with increased disability, increased risk of institutionalization, and with diminished survival rates. (author)

Hanford Site Beryllium Program: Past, Present, and Future - 12428

Energy Technology Data Exchange (ETDEWEB)

Fisher, Mark [CH2M Hill Plateau Remediation Company, Richland, Washington 99354 (United States); Garcia, Pete [U.S. Department of Energy - Richland Office, Richland, Washington 99352 (United States); Goeckner, Julie [U.S. Department of Energy - HQ, EMCBC, Cincinnati, Ohio 45202 (United States); Millikin, Emily [Washington Closure Hanford, Richland, Washington 99354 (United States); Stoner, Mike [Mission Support Alliance, Richland, Washington 99354 (United States)

2012-07-01

The U.S. Department of Energy (DOE) has a long history of beryllium use because of the element's broad application to many nuclear operations and processes. At the Hanford Site beryllium alloy was used to fabricate parts for reactors, including fuel rods for the N-Reactor during plutonium production. Because of continued confirmed cases of chronic beryllium disease (CBD), and data suggesting CBD occurs at exposures to low-level concentrations, the DOE decided to issue a rule to further protect federal and contractor workers from hazards associated with exposure to beryllium. When the beryllium rule was issued in 1999, each of the Hanford Site contractors developed a Chronic Beryllium Disease Prevention Program (CBDPP) and initial site wide beryllium inventories. A new site-wide CBDPP, applicable to all Hanford contractors, was issued in May, 2009. In the spring of 2010 the DOE Headquarters Office of Health, Safety, and Security (HSS) conducted an independent inspection to evaluate the status of implementation of the Hanford Site Chronic Beryllium Disease Prevention Program (CBDPP). The report identified four Findings and 12 cross-cutting Opportunities for Improvement (OFIs). A corrective action plan (CAP) was developed to address the Findings and crosscutting OFIs. The DOE directed affected site contractors to identify dedicated resources to participate in development of the CAP, along with involving stakeholders. The CAP included general and contractor-specific recommendations. Following initiation of actions to implement the approved CAP, it became apparent that additional definition of product deliverables was necessary to assure that expectations were adequately addressed and CAP actions could be closed. Consequently, a supplement to the original CAP was prepared and transmitted to DOE-HQ for approval. Development of the supplemental CAP was an eight month effort. From the onset a core group of CAP development members were identified to develop a mechanism

The analysis of beryllium-copper diffusion joint after HHF test

International Nuclear Information System (INIS)

Guiniatouline, R.N.; Mazul, I.V.; Rubkin, S.Y.

1995-01-01

The development of beryllium-copper joints which can withstand to relevant ITER divertor conditions is one of the important tasks at present time. One of the main problem for beryllium-copperjoints, is the inter-metallic layers, the strength and life time of joints significantly depends from the width and contents of the intermetallic layers. The objective of this work is to study the diffusion joint of TGP-56 beryllium to OFHC copper after thermal response and thermocyclic tests with beryllium-copper mockup. The BEY test were performed at e-beam facility (EBTS, SNLA). The following methods were used for analyses: the roentgenographic analysis; X-ray spectrum analysis; the fracture graphic analysis. During the investigation the followed studies were done: the analysis of diffusion boundary Be-Cu, which was obtained at the crossection of one of the tiles, the analysis of the debonded surfaces of a few beryllium tiles and corresponding copper parts; the analysis of upper surface of one of the tiles after HHF tests. The results of this work have showed that: the joint roentgenographic and elements analyses indicated the following phases in the diffusion zone: Cu 2 Be (∼170 μm), CuBe (∼30μm), CuBe 2 (∼1 μm) and solid solution of copper in beryllium. The phases Cu 2 Be, CuBe and solid solution of copper in beryllium were indicated using quantitative microanalysis and phases CuBe, CuBe 2 , Cu, Be - by roentgenographic analysis; the source of fracture (initial crack) is located in the central part of the tiles, the crack caused by the influence of residual stresses during cooling of a mock-up after fabrication and developed under the conditions of slow elastic-plastic growing during the process of thermal fatigue testing. The analysis gives the important data about joint's quality and also may be used for any type of joints and its comparison for ITER applications

Reactivity effects due to beryllium poisoning of BR2

International Nuclear Information System (INIS)

Kalcheva, S.; Ponsard, B.; Koonen, E.

2004-01-01

This paper illustrates the impact of the poisoning of the beryllium reflector on reactivity variations of the Belgian MTR BR2 in SCK.CEN. Detailed calculations by MCNP-4C of reactivity effects caused by strong neutron absorbers 3 He and 6 Li during reactor operation history are presented. The importance of beryllium poisoning for the accuracy of reactivity predictions is discussed. (authors)

Joining of beryllium by braze welding technique: preliminary results

Energy Technology Data Exchange (ETDEWEB)

Banaim, P.; Abramov, E. [Ben-Gurion Univ. of the Negev, Beersheba (Israel); Zalkind, S.; Eden, S.

1998-01-01

Within the framework of some applications, there is a need to join beryllium parts to each other. Gas Tungsten Arc Braze Welds were made in beryllium using 0.3 mm commercially Aluminum (1100) shim preplaced at the joint. The welds exhibited a tendency to form microcracks in the Fusion Zone and Heat Affected Zone. All the microcracks were backfilled with Aluminum. (author)

Extraction of beryllium sulfate by a long chain amine

International Nuclear Information System (INIS)

Etaix, E.S.

1968-01-01

The extraction of sulfuric acid in aqueous solution by a primary amine in benzene solution, 3-9 (diethyl) - 6-amino tri-decane (D.E.T. ) - i.e., with American nomenclature 1-3 (ethyl-pentyl) - 4-ethyl-octyl amine (E.P.O.) - has made it possible to calculate the formation constants of alkyl-ammonium sulfate and acid sulfate. The formula of the beryllium and alkyl-ammonium sulfate complex formed in benzene has next been determined, for various initial acidity of the aqueous solution. Lastly, evidence has been given of negatively charged complexes of beryllium and sulfate in aqueous solution, through the dependence of the aqueous sulfate ions concentration upon beryllium extraction. The formation constant of these anionic complexes has been evaluated. (author) [fr

Investigation of the beryllium ion-surface interaction

Energy Technology Data Exchange (ETDEWEB)

Guseva, M.I. [Kurchatov Inst., Moscow (Russian Federation); Birukov, A.Yu. [Kurchatov Inst., Moscow (Russian Federation); Gureev, V.M. [Kurchatov Inst., Moscow (Russian Federation); Daneljan, L.S. [Kurchatov Inst., Moscow (Russian Federation); Korshunov, S.N. [Kurchatov Inst., Moscow (Russian Federation); Martynenko, Yu.V. [Kurchatov Inst., Moscow (Russian Federation); Moskovkin, P.S. [Kurchatov Inst., Moscow (Russian Federation); Sokolov, Yu.A. [Kurchatov Inst., Moscow (Russian Federation); Stoljarova, V.G. [Kurchatov Inst., Moscow (Russian Federation); Kulikauskas, V.S. [M.V. Lomonosov University, Moscow (Russian Federation); Zatekin, V.V. [M.V. Lomonosov University, Moscow (Russian Federation)

1996-10-01

The energy and temperature dependence of self-sputtering yields of beryllium were measured. The energy dependence of the beryllium self-sputtering yield agrees well with that calculated by Eckstein et al. Below 770 K the self-sputtering yields are temperature independent; at T{sub irr.}>870 K the yield increases steeply. Beryllium samples were implanted at 370 K with monoenergetic 5 keV hydrogen ions and with a stationary hydrogen plasma power flux of about 5 MW/m{sup 2}. In the fluence range of 5 x 10{sup 22}-1.5 x 10{sup 25} m{sup -2} the depth profile is shifted towards the surface with increasing fluence and the concentration of trapped hydrogen atoms is reduced from 3.3 x 10{sup 21} to 7.4 x 10{sup 20} m{sup -2}. About 95% of the trapped hydrogen is located within bubbles and only {proportional_to}5% is trapped as atoms. With increasing implantation fluence the bubbles coalesce, producing channels through which hydrogen escapes. (orig.).

Restoring a neighborhood: Radium cleanup eases fears, rebuilds community

International Nuclear Information System (INIS)

Ranney, C.A.; Gaddis, D.M.

1993-01-01

Contaminated property is every homeowner's nightmare. That is even more true if the contamination is radioactive. But for the residents of the Monclair, West Orange, and Glen Ridge neighborhoods in Essex County, New Jersey, the nightmare became reality in the early 1980s. These three communities--representing some 750 modest, neatly kept homes--rested on radium-contaminated soils, the result of backfilling and dumping operations from 80 years ago. Residents first became alarmed in 1984, following regulatory action that triggered public awareness of excessive indoor radon gas readings, ambient gamma radiation 150 times normal levels and soil radium concentrations up to 2000 times greater than background. The worst contamination was limited to about 150 of the homes, but community concern--and the threat of the unknown--was tremendous. Not only were soils contaminated, but radon--a gas that forms during the decay of radium--with readings as high as 300 pCi/L in some homes was affecting air quality as well. Because both surficial and deeper soils were found to contain radioactive wastes, runoff and groundwater contamination was feared

Radium bearing waste disposal

International Nuclear Information System (INIS)

Tope, W.G.; Nixon, D.A.; Smith, M.L.; Stone, T.J.; Vogel, R.A.; Schofield, W.D.

1995-01-01

Fernald radium bearing ore residue waste, stored within Silos 1 and 2 (K-65) and Silo 3, will be vitrified for disposal at the Nevada Test Site (NTS). A comprehensive, parametric evaluation of waste form, packaging, and transportation alternatives was completed to identify the most cost-effective approach. The impacts of waste loading, waste form, regulatory requirements, NTS waste acceptance criteria, as-low-as-reasonably-achievable principles, and material handling costs were factored into the recommended approach

Beryllium thin films for resistor applications

Science.gov (United States)

Fiet, O.

1972-01-01

Beryllium thin films have a protective oxidation resistant property at high temperature and high recrystallization temperature. However, the experimental film has very low temperature coefficient of resistance.

Experience of beryllium blocks operation in the SM and MIR nuclear reactors useful for fusion

International Nuclear Information System (INIS)

Chakin, V.P.; Melder, R.R.; Belozerov, S.V.

2004-01-01

The results are presented concerning the examinations of state of beryllium blocks after the completion of their operation in the SM and MIR reactors. Both cracks and more significant mechanical damages are revealed in the irradiated beryllium blocks. Under neutron irradiation of beryllium radiation degradation of its physical and mechanical properties occurs. It shows itself in embrittlement, decrease of brittle strength level as well in worsening of thermal conductivity that leads to increase of thermal stresses into beryllium block. Under irradiation it takes place damage of beryllium microstructure, in particular, formation of radiation defects occurs in the form of dislocation loops and great amount of helium atoms. Optimization of beryllium radioactive waste storage is related to their preliminary surface and volumetric decontamination. (author)

Zone-refining of beryllium(II) acetylacetonate

International Nuclear Information System (INIS)

Yoshida, Isao; Kobayashi, Hiroshi; Ueno, Keihei

1975-01-01

Zone melting was applied to bis (acetylacetonato) beryllium(II), Be(AA) 2 , to remove trace metal constiutents. The effective distribution coefficient, k, of a minor component measured in a binary mixture with the majority of Be(AA) 2 , fell in the range of 0.4 to 0.8, while the value obtained in a multiple component mixture fell in the range of 0.8 to 0.9 except Zn(II)- and Ni(II) chelates. Cr(AA) 3 was concentrated upward in the direction of the zone travelling, and similar results were obtained with Cu(II)-, Co(III)- Fe(III)- and Al(III) acetylacetonates, while Zn(II)-, Ni(II)- and Mn(III) chelates were fractionated in the both ends of the column. On the other hand, when the zone was moved downward, the minor components were concentrated in the lower end of a column. Efficiency in zone refining was compared to each other between the upward- and downward zone travelling modes on the crude beryllium acetylacetonates obtained from a commercial reagent of beryllium nitrate, and the latter mode was found more effective in the concentration of trace components. Discussion was given on possible mechanisms resulting in the difference in the refining efficiency. (author)

Real-time monitoring of airborne beryllium, at OSHA limit levels, by time-resolved laser-induced breakdown spectroscopy

International Nuclear Information System (INIS)

Radziemski, L.J.; Loree, T.R.; Cremers, D.A.

1982-01-01

Real-time detection of beryllium particulate is being investigated by the new technique of laser-induced breakdown spectroscopy. For beryllium detection we monitor the 313.1-nm feature of once ionized beryllium (Be II). Numerous publications describe the technique, our beryllium results, and other applications. Here we summarize the important points and describe our experiments with beryllium

Influence of impurities in Beryllium on tritium breeding ratio

International Nuclear Information System (INIS)

Yamauchi, M.; Ochiai, K.; Verzilov, Y.; Ito, M.; Wada, M.; Nishitani, T.

2004-01-01

Several neutronics experiments simulating fusion blankets have been conducted with 14 MeV neutron source to assess the reliability of nuclear analysis codes. However, the analyses have not always presented good agreements so far between calculated and measured tritium production rates. One of the reasons was considered as impurities in beryllium which has negligibly small neutron absorption cross section in low energy range. Chemical compositions of beryllium were analyzed by Inductively Coupled Plasma (ICP) method, and a pulsed neutron decay experiment discovered that the macroscopic neutron absorption cross section for beryllium medium may be about 30% larger than the value calculated by the data specified by manufacturing company. The influence of the impurities on the calculations was studied on the basis of the fusion DEMO-reactor blanket design. As a result of the study, it was made clear that the impurities affect the local tritium production rates when the size of beryllium medium is more than 20-30 mean free paths (30-40 cm) in thickness. In case of some blanket designs that meet the above condition, the effect on tritium breeding ratio may become as large as about 4%. (author)

Influence of impurities in Beryllium on tritium breeding ratio

Energy Technology Data Exchange (ETDEWEB)

Yamauchi, M; Ochiai, K; Verzilov, Y; Ito, M; Wada, M; Nishitani, T [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

2004-03-01

Several neutronics experiments simulating fusion blankets have been conducted with 14 MeV neutron source to assess the reliability of nuclear analysis codes. However, the analyses have not always presented good agreements so far between calculated and measured tritium production rates. One of the reasons was considered as impurities in beryllium which has negligibly small neutron absorption cross section in low energy range. Chemical compositions of beryllium were analyzed by Inductively Coupled Plasma (ICP) method, and a pulsed neutron decay experiment discovered that the macroscopic neutron absorption cross section for beryllium medium may be about 30% larger than the value calculated by the data specified by manufacturing company. The influence of the impurities on the calculations was studied on the basis of the fusion DEMO-reactor blanket design. As a result of the study, it was made clear that the impurities affect the local tritium production rates when the size of beryllium medium is more than 20-30 mean free paths (30-40 cm) in thickness. In case of some blanket designs that meet the above condition, the effect on tritium breeding ratio may become as large as about 4%. (author)

Evaluation of the hazard associated with fabricating beryllium copper alloys

International Nuclear Information System (INIS)

Senn, T.J.

1977-01-01

Beryllium-copper alloys should be considered toxic materials and proper controls must be used when they are machined, heated, or otherwise fabricated. Air samples should be taken for each type of fabrication to determine the worker's exposure and the effectiveness of the controls in use. It has been shown that aerosols containing beryllium are generated during the four methods of fabrication tested, and that these aerosols can be reduced through local exhaust to undetectable levels. Considering the acute, chronic and possibly carcinogenic effects of exposure to beryllium, effective controls should be required because they are feasible both technologically and economically. The health hazards and control measures are reviewed

Historical perspectives on the uses and health risks of beryllium

International Nuclear Information System (INIS)

Preuss, O.P.

1985-01-01

Unawareness of the health risks of beryllium resulted in a decade of unmitigated exposure of several thousand workers and numerous cases of beryllium disease in employees and nearby residents. Subsequent adoption of exposure limits and their implementation with effective technical controls reduced the occurrence of new cases, which were mainly due to accidental exposures, to a minimum. The fact that continuously growing production and consumption did not alter this trend demonstrates the effectiveness of the present threshold limit value. It shows that the potential health hazard can be well contained and that beryllium can be produced and fabricated without undue risk to employees or the general public

Operational experience with the JET beryllium evaporators in the J1W test bed

International Nuclear Information System (INIS)

Peacock, A.T.; Dietz, K.J.; Israel, G.; Jensen, H.S.; Johnson, A.; Pick, M.A.; Saibene, G.; Sartori, R.

1989-01-01

Four beryllium evaporators were fitted onto the JET vessel during March 1989. These evaporators are planned to give the first introduction of beryllium into the JET machine to study the effect of using beryllium as a first wall material. Over 200 hours operational experience with such an evaporator had been gained on a test bed facility in which the evaporation rate, radial evaporant distribution and head operating temperature had been determined. The results obtained on this facility with two different heat materials, sintered S-65B and vacuum cast beryllium are described. The test vessel has also been used to conduct beryllium wall pumping experiments using the ''Langmuir effect''. The initial results of these experiments will be described. (author)

Mineral composition and heavy metal contamination of sediments originating from radium rich formation water.

Science.gov (United States)

Bzowski, Zbigniew; Michalik, Bogusław

2015-03-01

Radium rich formation water is often associated with fossil fuels as crude oil, natural gas and hard coal. As a result of fossil fuels exploitation high amount of such water is released into environment. In spite of the high radium content such waters create a serious radiation risk neither to humans nor biota directly. First and foremost due to very high mineralization they are not drinkable at all. But after discharge chemical and physical conditions are substantially changed and sediments which additionally concentrated radium are arising. Due to features of technological processes such phenomenon is very intensive in underground coal mining where huge volume of such water must be pumped into surface in order to keep underground galleries dry. Slightly different situation occurs in oil rigs, but finally also huge volume of so called process water is pumped into environment. Regardless their origin arising sediments often contain activity concentration of radium isotopes exceeding the clearance levels set for naturally occurring radioactive materials (NORM) (Council Directive, 2013). The analysis of metals and minerals content showed that besides radioactivity such sediments contain high amount of metals geochemically similar to radium as barium, strontium and lead. Correlation analysis proved that main mechanism leading to sediment creation is co-precipitation radium with these metals as a sulfate. The absorption on clay minerals is negligible even when barium is not present in significant quantities. Owing to very low solubility of sulfates radium accumulated in this way should not migrate into environment in the neighborhood of a site where such sediment were deposited. Copyright © 2014 Elsevier Ltd. All rights reserved.

Multiple myeloma, leukemia, and breast cancer among the US radium dial workers

International Nuclear Information System (INIS)

Stebbings, J.H.; Lucas, H.F.; Stehney, A.F.

1983-01-01

The relationships of radium exposure to mortality from multiple myeloma, leukemia, and breast cancer were studied in three cohorts of female dial workers defined by year of first employment. Mortality was compared with that expected from US white female rates, with and without adjustment for local mortality rates. Dose-response relationships of these cancers to systemic intake of radium were determined in workers whose body burdens had been measured in vivo since 1955. Incident cases of multiple myeloma occurred in the pre-1930 cohort; however, analyses of body burdens and durations of employment suggest that external radiation was more likely to have been responsible than was internal radium. Leukemia incidence and mortality have not been elevated overall among the female dial workers, either in the pre-1930 or the post-1930 cohorts, but cases have tended to occur early and in subjects with higher body burdens. Extensive analyses of breast cancer data have uncovered several observations weighing against a causal interpretation of the association between radium and breast cancer

Lymphoblastogenesis in response to phytohemagglutinin in radium patients: quantitative aspects and reproducibility

International Nuclear Information System (INIS)

Serio, C.S.; Henning, C.B.; Lloyd, E.L.

1978-01-01

Lymphocyte stimulation by different concentrations of phytohemmagglutinin (PHA) provided a profile of lymphocyte responsiveness in 5 normal subjects and 40 radium dial painters. This profile will, hopefully, improve detection of lymphocyte defects in patients with impairment of cellular immunity. When a suboptimal dose (0.15 μg PHA-protein) was used, decreased lymphocyte responsiveness was observed in patients with high body burdens of 226 Ra (> 0.1 μCi) compared with patients with low body burdens (< 0.1 μCi) and normal subjects. At all other PHA concentrations, the lymphocyte responsiveness was not significantly different in these three groups. A decrease in lymphocyte response was found with age in both normal controls and in the radium patients, but the decrease appeared to be somewhat greater in the radium patients above 50 years of age. To test the significance of these findings, larger numbers of control subjects in the higher age groups and low body burden radium patients known not to be on any type of medication will have to be examined

Spent sealed radium sources conditioning in Latin America

International Nuclear Information System (INIS)

Mourao, R.P.

1999-01-01

The management of spent sealed sources is considered by the International Atomic Energy Agency (IAEA) one of the greatest challenges faced by nuclear authorities today, especially in developing countries. One of the Agency's initiatives to tackle this problem is the Spent Radium Sources Conditioning Project, a worldwide project relying on the regional co-operation between countries. A team from the Brazilian nuclear research institute Centro de Desenvolvimento da Tecnologia Nuclear (CDTN) was chosen as the expert team to carry out the operations in Latin America; since December 1996 radium sources have been safely conditioned in Uruguay, Nicaragua, Guatemala, Ecuador and Paraguay. A Quality Assurance Program was established, encompassing the qualification of the capsule welding process, written operational procedures referring to all major steps of the operation, calibration of monitors and information retrievability. A 200L carbon steel drum-based packaging concept was used to condition the sources, its cavity being designed to receive the lead shield device containing stainless steel capsules with the radium sources. As a result of these operations, a total amount of 2,897 mg of needles, tubes, medical applicators, standard sources for calibration, lightning rods, secondary wastes and contaminated objects were stored in proper conditions and are now under control of the nuclear authorities of the visited countries

Spent sealed radium sources conditioning in Latin America

International Nuclear Information System (INIS)

Mourao, Rogerio Pimenta

1999-01-01

The management of spent sealed sources is considered by the IAEA one of the greatest challenges faced by nuclear authorities today, especially in developing countries. One of the Agency's initiatives to tackle this problem is the 'Spent Radium Sources Conditioning Project', a worldwide project relying on the regional cooperation between countries. A CDTN team was chooses as the expert team to carry out the operations in Latin America; since Dec 96 radium sources have been safely conditioned in Uruguay, Nicaragua, Guatemala and Ecuador. A Quality Assurance Program was established, encompassing the qualification of the capsule welding process, written operational procedures referring to all major steps of the operation, calibration of monitors and information retrievability. A 200L carbon steel drum-based packaging concept was used to condition the sources, its cavity being designed to receive the lead shield device containing stainless steel capsules with the radium sources. As a result of these operations, a total amount of 2,629 mg (approx. 98 GBq) of needles, tubes, medical applicators, standard sources for calibration, lightning rods, secondary wastes (generated during the operations) and contaminated objects were stored in proper conditions and are now under control, of the nuclear authorities of the visited countries. (author)

Interaction of radium with freshwater sediments and their mineral components Pt. 4

International Nuclear Information System (INIS)

Benes, P.; Strejc, P.

1986-01-01

A radiotracer method was used for investigating the adsorption and desorption of radium on stream sediments under conditions similar to those prevailing in waste and surface waters. The effects of pH, ionic strength and Casup(2+) or SOsub(4)sup(2+) ions were studied. The results were compared with analogous data characterizing radium interaction with model solids representing components of the sediments. It was found that the adsorption affinity of the sediments for radium cannot be easily derived from their composition or other properties. No simple correlation with specific surface area, organic matter, oxidic coatings or other components of the sediments was observed. However, an exceptional role of barite (barium sulfate) in the sediments was noted. (author)

Use of carriers for to electrodeposited radium 226; Utilizacion de portadores para electrodepositar radio 226

Energy Technology Data Exchange (ETDEWEB)

Iturbe, J.L

1991-10-15

The form of the energy distribution of a monoenergetic alpha particle starting from some emitting source of these particles, it depends on the quantity of material that its cross before being detected. Some authors deposit to the radium-226 by means of direct evaporation of the solution on metallic supports, on millipore paper and by electrodeposition. Some other ones place the radium solution in scintillation liquid, to quantify it by this technique. The objective of the present work is using carriers with the same oxidation state of the radium, that is to say of 2{sup +}, for treating to be electrodeposited to the radium-226 with the biggest possible percentage for later use the alpha spectroscopy technique to quantify it. The carriers that have been used until its they are barium and zinc in form of barium chloride, zinc nitrate and zinc sulfate. The first results indicate that with the zinc solution a yield of 40% of electrodeposited radium has been reached. (Author)

Natural radium and radon tracers to quantify water exchange and movement in reservoirs

Science.gov (United States)

Smith, Christopher G.; Baskaran, Mark

2011-01-01

Radon and radium isotopes are routinely used to quantify exchange rates between different hydrologic reservoirs. Since their recognition as oceanic tracers in the 1960s, both radon and radium have been used to examine processes such as air-sea exchange, deep oceanic mixing, benthic inputs, and many others. Recently, the application of radon-222 and the radium-quartet (223,224,226,228Ra) as coastal tracers has seen a revelation with the growing interest in coastal groundwater dynamics. The enrichment of these isotopes in benthic fluids including groundwater makes both radium and radon ideal tracers of coastal benthic processes (e.g. submarine groundwater discharge). In this chapter we review traditional and recent advances in the application of radon and radium isotopes to understand mixing and exchange between various hydrologic reservoirs, specifically: (1) atmosphere and ocean, (2) deep and shallow oceanic water masses, (3) coastal groundwater/benthic pore waters and surface ocean, and (4) aquifer-lakes. While the isotopes themselves and their distribution in the environment provide qualitative information about the exchange processes, it is mixing/exchange and transport models for these isotopes that provide specific quantitative information about these processes. Brief introductions of these models and mixing parameters are provided for both historical and more recent studies.

Report of a technical evaluation panel on the use of beryllium for ITER plasma facing material and blanket breeder material

Energy Technology Data Exchange (ETDEWEB)

Ulrickson, M.A. [ed.] [Sandia National Labs., Albuquerque, NM (United States); Manly, W.D. [Oak Ridge National Lab., TN (United States); Dombrowski, D.E. [Brush Wellman, Inc., Cleveland, OH (United States)] [and others

1995-08-01

Beryllium because of its low atomic number and high thermal conductivity, is a candidate for both ITER first wall and divertor surfaces. This study addresses the following: why beryllium; design requirements for the ITER divertor; beryllium supply and unirradiated physical/mechanical property database; effects of irradiation on beryllium properties; tritium issues; beryllium health and safety; beryllium-coolant interactions and safety; thermal and mechanical tests; plasma erosion of beryllium; recommended beryllium grades for ITER plasma facing components; proposed manufacturing methods to produce beryllium parts for ITER; emerging beryllium materials; proposed inspection and maintenance techniques for beryllium components and coatings; time table and costs; and the importance of integrating materials and manufacturing personnel with designers.

Report of a technical evaluation panel on the use of beryllium for ITER plasma facing material and blanket breeder material

International Nuclear Information System (INIS)

Ulrickson, M.A.; Manly, W.D.; Dombrowski, D.E.

1995-08-01

Beryllium because of its low atomic number and high thermal conductivity, is a candidate for both ITER first wall and divertor surfaces. This study addresses the following: why beryllium; design requirements for the ITER divertor; beryllium supply and unirradiated physical/mechanical property database; effects of irradiation on beryllium properties; tritium issues; beryllium health and safety; beryllium-coolant interactions and safety; thermal and mechanical tests; plasma erosion of beryllium; recommended beryllium grades for ITER plasma facing components; proposed manufacturing methods to produce beryllium parts for ITER; emerging beryllium materials; proposed inspection and maintenance techniques for beryllium components and coatings; time table and costs; and the importance of integrating materials and manufacturing personnel with designers

DETERMINING BERYLLIUM IN DRINKING WATER BY GRAPHITE FURNACE ATOMIC ABSORPTION SPECTROSCOPY

Science.gov (United States)

A direct graphite furnace atomic absorption spectroscopy method for the analysis of beryllium in drinking water has been derived from a method for determining beryllium in urine. Ammonium phosphomolybdate and ascorbic acid were employed as matrix modifiers. The matrix modifiers s...

Determination of radium isotopes by BaSO4 coprecipitation for the preparation of alpha-spectrometric sources

International Nuclear Information System (INIS)

Lozano, J.C.; Fernandez, F.; Gomez, J.M.G.

1997-01-01

A coprecipitation procedure for the preparation of α-spectrometric sources for radium, using BaSO 4 as carrier, has been applied to the determination of alpha radium isotopes in water samples. The use of 133 Ba as a suitable tracer for radium determination and possible losses of radon isotopes from the sources are studied and discussed. (author)

Skeletal and tissue lesions resulting from exposure to radium and fission products

International Nuclear Information System (INIS)

Warren, S.

1973-01-01

The chief effects of absorbed radionuclides and external radiation are radiation osteitis, disturbed bone growth, myelofibrosis, and bone tumors. The lesions in part are dependent on localization and character of the radiation, in part on dose. Data on radium were derived from dial painters, radium chemists and those treated some years ago by oral or parenteral administration. (U.S.)

Thermal fatigue of beryllium

International Nuclear Information System (INIS)

Deksnis, E.; Ciric, D.; Falter, H.

1995-01-01

Thermal fatigue life of S65c beryllium castellated to a geometry 6 x 6 x (8-10)mm deep has been tested for steady heat fluxes of 3 MW/m 2 to 5 MW/m 2 and under pulsed heat fluxes (10-20 MW/m 2 ) for which the time averaged heat flux is 5 MW/m 2 . These tests were carried out in the JET neutral beam test facility A test sequence with peak surface temperatures ≤ 600 degrees C produced no visible fatigue cracks. In the second series of tests, with T max ≤ 750 degrees C evidence for fatigue appeared after a minimum of 1350 stress cycles. These fatigue data are discussed in view of the observed lack of thermal fatigue in JET plasma operations with beryllium PFC. JET experience with S65b and S65c is reviewed; recent operations with Φ = 25 MW/m 2 and sustained melting/resolidification are also presented. The need for a failure criterion for finite element analyses of Be PFC lifetimes is discussed

Corrosion of beryllium oxide

International Nuclear Information System (INIS)

Elston, J.; Caillat, R.

1958-01-01

Data are reported on the volatilization rate of beryllium oxide in moist air depending on temperature and water vapour concentration. They are concerned with powder samples or sintered shapes of various densities. For sintered samples, the volatilization rate is very low under the following conditions: - temperature: 1300 deg. C, - water vapour concentration in moist air: 25 g/m 3 , - flow rate: 12 I/hour corresponding to a speed of 40 m/hour on the surface of the sample. For calcinated powders (1300 deg. C), grain growth has been observed under a stream of moist air at 1100 deg. C. For instance, grain size changes from 0,5 to at least 2 microns after 500 hours of exposure at this temperature. Furthermore, results data are reported on corrosion of sintered beryllium oxide in pressurized water. At 250 deg. C, under a pressure of 40 kg/cm 2 water is very slightly corrosive; however, internal strains are revealed. Finally, some features on the corrosion in liquid sodium are exposed. (author) [fr

Distribution of radon and radium in the ocean and its bearing on some oceanographic problems

International Nuclear Information System (INIS)

Miyake, Y.; Sugimura, Y.; Saruhashi, K.

1980-01-01

Radon and radium contents in seawater near the ocean floor and in the surface layer of the ocean were studied. The results showed a fairly large amount of excess of radon over radium (1520 to 315%) near the ocean floor. The vertical eddy-diffusion coefficient, D, near the seabed was calculated from a vertical distribution of the excess amount of radon. In the surface layer of the ocean, a remarkable deficiency of radon with respect to radium (50 to 70%) was observed. The mass balance of radium in the mixed layer was considered using a box model. The results showed that the residence time of radon in the mixed layer was about 8 days

Leachability characteristics of beryllium in redmud waste and its stabilization in cement

International Nuclear Information System (INIS)

Saradhi, I.V.; Mahadevan, T.N.; Krishnamoorthy, T.M.

1999-01-01

More than 70% of the beryl ore processed by the Beryllium Metal Plant at the BARC Vashi Complex ends up as redmud waste. The presence of significant quantities (0.4 to 0.8%) of beryllium in the redmud qualifies it as hazardous requiring safe handling, storage and disposal. The waste also contains 0.09% of water soluble fluoride. The various standard protocol of procedures were employed to estimate the leachability of beryllium from redmud for both short term and long term periods. Nearly 50% of beryllium present in redmud is leachable in water. We have tried the stabilization of redmud using portland cement. The proportion of redmud to cement was in the ratio of 1:1, 1:2 and 1:4. The blocks were cast, cured and used in the leachability experiments using standard protocols as above. The results of the TCLP test gave the levels of beryllium well below the standard limits in the TCLP extract of cement stabilized waste indicating the suitability of stabilization of redmud with cement whereas that of raw waste (redmud) are much higher than the prescribed limits. The total leach percent of beryllium in 1:2 block is 0.05% over period of 164 days whereas 1:1 and 1:4 gave a leach percent of 0.26 and 0.15% respectively. The DLT results indicate, diffusion controlled release of beryllium from the cement stabilized redmud blocks. The effective diffusion coefficient of beryllium obtained from the modelling study is 10 orders of magnitude less than the molecular diffusion coefficient of beryllium indicating the effectiveness of cement stabilization. From the detailed experiments performed, it is felt that 1:2 proportion of redmud and cement will be the best suited option for stabilization of redmud waste. The 1:1 proportion of redmud to cement mixture which could not be cast into compact cement blocks also exhibited very low leachability characteristics similar to 1:2 and 1:4 and can be be favourably considered for stabilization in case of space constraints at storage sites. The

Physicochemical characteristics of aerosol particles generated during the milling of beryllium silicate ores: implications for risk assessment.

Science.gov (United States)

Stefaniak, Aleksandr B; Chipera, Steve J; Day, Gregory A; Sabey, Phil; Dickerson, Robert M; Sbarra, Deborah C; Duling, Mathew G; Lawrence, Robert B; Stanton, Marcia L; Scripsick, Ronald C

2008-01-01

Inhalation of beryllium dusts generated during milling of ores and cutting of beryl-containing gemstones is associated with development of beryllium sensitization and low prevalence of chronic beryllium disease (CBD). Inhalation of beryllium aerosols generated during primary beryllium production and machining of the metal, alloys, and ceramics are associated with sensitization and high rates of CBD, despite similar airborne beryllium mass concentrations among these industries. Understanding the physicochemical properties of exposure aerosols may help to understand the differential immunopathologic mechanisms of sensitization and CBD and lead to more biologically relevant exposure standards. Properties of aerosols generated during the industrial milling of bertrandite and beryl ores were evaluated. Airborne beryllium mass concentrations among work areas ranged from 0.001 microg/m(3) (beryl ore grinding) to 2.1 microg/m(3) (beryl ore crushing). Respirable mass fractions of airborne beryllium-containing particles were 80% in high-energy input areas (beryl melting, beryl grinding). Particle specific surface area decreased with processing from feedstock ores to drumming final product beryllium hydroxide. Among work areas, beryllium was identified in three crystalline forms: beryl, poorly crystalline beryllium oxide, and beryllium hydroxide. In comparison to aerosols generated by high-CBD risk primary production processes, aerosol particles encountered during milling had similar mass concentrations, generally lower number concentrations and surface area, and contained no identifiable highly crystalline beryllium oxide. One possible explanation for the apparent low prevalence of CBD among workers exposed to beryllium mineral dusts may be that characteristics of the exposure material do not contribute to the development of lung burdens sufficient for progression from sensitization to CBD. In comparison to high-CBD risk exposures where the chemical nature of aerosol

Radium variability produced by shelf-water transport and mixing in the western Gulf of Mexico

International Nuclear Information System (INIS)

Reid, D.F.

1984-01-01

226 Ra and 228 Ra exhibit significant temporal and spatial variability in the near-surface western Gulf of Mexico. Concentrations of both isotopes during March 1976 were approx. 22 to 26% greater than those observed during February 1973. It is shown that analytical differences cannot account for this increase. Consideration of radium levels in the western Caribbean Sea indicates that there must be an internal source of radium that has a significant but temporally variable influence on near-surface radium concentrations in the western Gulf. Comparisons of radium, salinity, and temperature data from 1973 and 1976 provide evidence that advective transport and mixing of radium-rich shelf water with the interior water column of the western basin is responsible for the variability. By plotting 228 Ra vs 226 Ra from this region, estimates of the apparent shelf-water component in the upper water column can be made. The results indicate 36% over the northern slope, 10 to 18% in the central western Gulf, and 3 to 7% over Campeche Bank. In addition to explaining observed short-term variations of radium in this region, this information should be useful for environmental impact assessments concerned with industrial discharges on the northern shelf. (author)

Assessment of the beryllium lymphocyte proliferation test using statistical process control.

Science.gov (United States)

Cher, Daniel J; Deubner, David C; Kelsh, Michael A; Chapman, Pamela S; Ray, Rose M

2006-10-01

Despite more than 20 years of surveillance and epidemiologic studies using the beryllium blood lymphocyte proliferation test (BeBLPT) as a measure of beryllium sensitization (BeS) and as an aid for diagnosing subclinical chronic beryllium disease (CBD), improvements in specific understanding of the inhalation toxicology of CBD have been limited. Although epidemiologic data suggest that BeS and CBD risks vary by process/work activity, it has proven difficult to reach specific conclusions regarding the dose-response relationship between workplace beryllium exposure and BeS or subclinical CBD. One possible reason for this uncertainty could be misclassification of BeS resulting from variation in BeBLPT testing performance. The reliability of the BeBLPT, a biological assay that measures beryllium sensitization, is unknown. To assess the performance of four laboratories that conducted this test, we used data from a medical surveillance program that offered testing for beryllium sensitization with the BeBLPT. The study population was workers exposed to beryllium at various facilities over a 10-year period (1992-2001). Workers with abnormal results were offered diagnostic workups for CBD. Our analyses used a standard statistical technique, statistical process control (SPC), to evaluate test reliability. The study design involved a repeated measures analysis of BeBLPT results generated from the company-wide, longitudinal testing. Analytical methods included use of (1) statistical process control charts that examined temporal patterns of variation for the stimulation index, a measure of cell reactivity to beryllium; (2) correlation analysis that compared prior perceptions of BeBLPT instability to the statistical measures of test variation; and (3) assessment of the variation in the proportion of missing test results and how time periods with more missing data influenced SPC findings. During the period of this study, all laboratories displayed variation in test results that

Uranium,Radium and Iron Absorption from Liquid Waste Uranium Ore Processing by Zeolite

International Nuclear Information System (INIS)

Wismawati, T; Sorot sudiro, A; Herjati, T

1998-01-01

The aim of this work is to determine zeolites sorption capacity and the distribution coefficient of uranium, radium, and iron in zeolite-liquid waste system. Mineralogical composition of zeolite used in the experiment has been determine by examining the thin sections of zeolite grains under a microscope. Zeolite has ben activated by the dilute sulfuric acid or sodium hydroxide solution. The results show that the use of 0.25 N sodium hydroxide solution could be optimizing the zeolite for uranium and iron ions sorption and that of 0.1 N sulfuric acid solution is for radium sorption. The re-activation process has been carried out in three hours. Under such a condition, the sorption efficiency of zeolite to those ions have been known to be 45.85% for uranium, 96.63 % for iron and 87.80 % for radium. The distribution coefficients of uranium, radium and iron ion in zeolite-liquid waste system have been calculated 0.85, 7.02, and 28.65 ml/g respectively