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Sample records for ra-226 conditioning waste

  1. Mobility of Ra-226 and Heavy Metals (U, Th and Pb) from Pyritic Uranium Mine Tailings under Sub-aqueous Disposal Conditions - 59283

    Dave, Nand K.

    2012-01-01

    All uranium mines in the Elliot Lake uranium mining district of north-central Ontario, Canada, have been closed due to low ore grade and prevailing market conditions. A majority of the waste management facilities have been rehabilitated and decommissioned with in-situ shallow water covers to minimize sulphide oxidation, and hence acid generation and release of metal enriched effluents. Laboratory lysimeter studies were undertaken to evaluate the leaching characteristics and mobility of Ra-226 and other heavy metals (U, Th and Pb) from pyritic uranium mine tailings under sub-aqueous disposal conditions for assessing the long-term radiological stability of such waste repositories. The experiments were conducted using three types of un-oxidized tailings: fine, coarse and gypsum depleted mill total tailings. Shallow water covers of depth ∼ 0.3 m were established using natural lake water. The leaching characteristics of radium and other major and trace metals were determined by monitoring both surface and pore water qualities as a function of time. The results showed that Ra-226 was leached from surface of the submerged tailings and released to both surface water and shallow zone pore water during initial low sulphate ion concentration of the surface water cover in all three cases. The release of Ra-226 was further enhanced with the onset of weak acidic conditions in the surface water covers of both coarse and gypsum depleted mill total tailings. With additional acid generation and increasing sulphate and iron concentrations, the dissolved Ra-226 concentrations in the water covers of these tailings gradually decreased back to low levels. Pb was also leached and mobilized with the development of moderate acidic conditions at the surface of the submerged coarse and gypsum deplete tailings. No leaching of U and Th was observed. (authors)

  2. The use of bitumen for storing radioactive waste resulting from oil industry containing Ra-226

    Takriti, S.; Shweikani, R.; Abdulhafiz, M.; Salman, M.

    2009-12-01

    The releases of radon gas from NORM waste contained in two different forms of bitumen samples have been investigated. The artificial NORM source samples were made by mixing NORM with bitumen. The sources surrounded by different thickness of bitumen layers to prepare the first form of samples. While, the NORM powder was put inside bitumen samples prepared as a cylindrical shape with different thickness. The results showed that the release of radon from the bitumen samples was different in case of sources and powder. The results illustrated that the release of radon from the bitumen samples was decrees linearly with the samples thicknesses (in both cases source and powder). On the other hand, the release from the cement samples was proportional inversely with the different thickness (for comparison). In addition, many other supporting experiments were performed, as γ-ray spectroscopy measurements showed that the cement is better than the bitumen in shielding process, while the bitumen is better than cement to prevent the releases of radon. (authors)

  3. Ra-226 bioaccumulation and growth indices in fish.

    Shi, Xiaopei; Smith, Richard; Seymour, Colin; Mothersill, Carmel

    2017-06-01

    To determine the accumulated activity of Ra-226 in fathead minnows fed with environmentally relevant levels of Ra-226 for 5 months in water at 20 °C, and to evaluate the influence of this level of Ra-226 on the growth of fathead minnows. Fathead minnows were fed with fish food containing 10-10,000 mBq/g Ra-226 for 5 months. At the end of the experiment, the fish were sacrificed, flash frozen in liquid nitrogen and kept at -20 °C. Longitudinal sections of 40 μm thickness were cut at the middle of the fish body using a cryostat. The activity of Ra-226 in each section was determined using autoradiography with a nuclear track detector CR-39. According to the weight and the width of the fish, the activity of Ra-226 in the whole fish body could be estimated. In addition, the length and the weight of the fish were measured and the condition factor was calculated to evaluate the growth and fitness of the fish. There is a positive but non-linear relationship between the accumulated activity of Ra-226 in fish body and the concentration of Ra-226 in fish food. The highest activity of Ra-226 accumulated in fish body was found from fish fed with 10,000 mBq/g Ra-226 food. This was calculated as 256.4 ± 49.1 mBq/g, p fish fed with food containing lower concentration of Ra-226 (up to 1000 mBq/g), the bioaccumulation of Ra-226 in the body saturated. The Ra-226 concentration factor (CF) for fish was inversely proportional to the Ra-226 activity in food, and the highest CF value was 2.489, obtained from the lowest dietary Ra-226 activity (10 mBq/g). In addition, condition factors (K) of fish in all Ra-226-treated groups were significantly lower than those of the controls. The results show that the bioaccumulation of Ra-226 in fish is not simply related to the dietary Ra-226 activity, and has a saturation value when the dietary activity is low. In addition, the environmental level of Ra-226 in the fish food has a small adverse effect on the growth and fitness of fathead

  4. Implementation of radon measurements to evaluate the suitability of using cement containers for storing radioactive waste containing Ra-226

    Shweikani, R.; Kheituo, M.; Hushari, M.; Ali, A. F.

    2003-12-01

    This work aimed at studying radon diffusion through walls of cubic cement containers containing inside radioactive waste rich in Radium-226. In addition, the effect of the wall thickness on radon exhalation and external gamma exposure were also studded. Cubic cement molds were prepared with different dimensions ranged from 5 to 11 cm containing central cubic holes to contain the radioactive materials with dimensions ranged from 2 to 7 cm. The thicknesses of the walls were varied from 1 to 4 cm. Radon exhalation was studied by placing each pre-prepared cement specimen in a tightly closed glass container (desiccators, volume 7 liters) provided with input and output gas system circulation for one week. Active method (Lucas cell) was used to measure the concentration of radon in the container. It was noticed that radon concentration increased with the increase of the radioactive materials inside the specimens. This was simply explained as it is due to the increase of the amount of radium-226 in the specimen with will definitely lead to the increase of radon production. In addition, it was noticed that radon concentration were increased by increasing the thickness of the specimen wall for fixed amount of the radioactive materials inside. This result was unexpected. Therefore, many attempts were performed to explain it. For that, the mechanism of cement solidifications and structure of cement after solidification were studied. The conditions which affect the size and number of the formed pores in the specimens were also studied assuming that increasing the wall thickness will increase porosity and lead to the increase diffusion paths. It was concluded that it is possible to use the cubic cement containers to stop gamma radiation from the radioactive materials, but it is not possible to use them to stop radon unless special arrangements are performed. (author)

  5. Leaching of RA-226 contaminated gravel using different aqueous treatments

    Mamoon, A; Abulfaraj, W H; Sohsah, M A [King Abdulaziz University, Jeddah, Saudi Arbabia (Saudi Arabia)

    1997-12-31

    Investigation of the efficiencies of different aqueous leaching treatments was carried out on gravel artificially contaminated with Ra-226. The extent of leaching efficiency was determined in terms of Ra-226 and its daughter Rn-222. Liquid scintillation counting using high efficiency mineral oil based liquid scintillator was the technique adopted for measuring Ra-226 and Rn-222 leached off the contaminated gravel. Water, dilute solutions of barium chloride and HCl were used as leachants. Different masses of gravel were leached with 200 mL of leachant for various contact time periods. The leached Rn-222 activity measured was plotted vs the decay factor e; from which Rn-222 and Ra-226 originally present in the sample were determined. Several leaching parameters were tested; namely type of leachant, leachant volume/gravel mass ratio, leachant contact time, effect of varying Ba Cl{sub 2} concentration, and successive leaching. Optimization of the leaching parameters for desorption of Ra-226 off the contaminated gravel under laboratory conditions may help determine the ideal conditions for remediating soil contaminated with radium or chemically similar radionuclides. 7 figs.

  6. The dose exposure of the environmental population by natural and released Ra-226 from an uranium mine prospect

    Schuettelkopf, H.; Kiefer, H.

    1980-08-01

    The concentration of natural Ra-226 in the environment of Baden-Baden was determined in samples of drinking water, surface water, sediments, soil, fish, milk and other food. The results partly are higher than normal caused by a local uranium deposit. Ra-226 releases with waste water from an uranium mine prospect are measured. The Ra-226 concentrations in creeks and sediments partly caused by this waste water were determined. Ra-226 concentrations in soil and plant samples collected on uranium ore dumps were partly much higher than in the environment. (orig.) [de

  7. Ra-226 concentrations in the Lower Weser region in the vicinity of a pollution source

    Lauer, R.

    1981-01-01

    Near Nordenham at the lower Weser Ra-containing waste water is discharged from a fertilizer factory. The measurements are restricted to Ra-analysis and the Ra in fish, sediment, and river water samples (Ra-226). (DG) [de

  8. A theoretical model for the production of Ac-225 for cancer therapy by neutron capture transmutation of Ra-226.

    Melville, G; Melville, P

    2013-02-01

    Radium needles that were once implanted into tumours as a cancer treatment are now obsolete and constitute a radioactive waste problem, as their half-life is 1600 years. We are investigating the reduction of radium by transmutation by bombarding Ra-226 with high-energy neutrons from a neutron source to produce Ra-225 and hence Ac-225, which can be used as a generator to produce Bi-213 for use in 'Targeted Alpha Therapy' for cancer. This paper examines the possibility of producing Ac-225 by neutron capture using a theoretical model in which neutron energy is convoluted with the corresponding neutron cross sections of Ra-226. The total integrated yield can then be obtained. This study shows that an intense beam of high-energy neutrons could initiate neutron capture on Ra-226 to produce Ra-225 and hence practical amounts of Ac-225 and a useful reduction of Ra-226. Copyright © 2012 Elsevier Ltd. All rights reserved.

  9. Ra-226 concentrations in blueberries Vaccinium angustifolium Ait. near an inactive uranium tailings site in Elliot Lake, Ontario, Canada

    Dave, N.K.; Lim, T.P.; Cloutier, N.R.

    1985-01-01

    Ra-226 concentrations were measured in blueberries growing around the Stanrock uranium tailings area near Elliot Lake, Ontario, Canada. Elevated levels of total Ra-226 ranging between 20 to 290 mBq g -1 were observed in samples collected within 500 m from the tailings. Highest levels, approx. 285 mBq g -1 , were observed in a sample collected on a tailings spill. For sites located more than 500 m away in the upwind direction, and those situated at distances greater than 1 km downwind from the waste pile, the total Ra-226 concentrations approached background levels which were measured as 2 to 6 mBq g -1 . Approximately 17% of the total Ra-226 measured was removable by washing the samples with distilled water. Wind dispersal of the tailings material and its deposition in the form of dust on blueberries was believed to be responsible for the external contamination. Based on the ICRP recommended dose limits for oral intake of Ra-226, it was calculated that approximately 160 kg a -1 , 3350 kg a -1 and 47 kg a -1 of washed blueberries from inside and outside the influenced zone, and from the tailings spill site, respectively, would need to be consumed before the individual annual limit for the general public was exceeded. (author)

  10. Production of Ac-225 for cancer therapy by photon-induced transmutation of Ra-226.

    Melville, G; Meriarty, H; Metcalfe, P; Knittel, T; Allen, B J

    2007-09-01

    The increasing application of Ac-225 for cancer therapy indicates the potential need for its increased production and availability. The production of Ac-225 has been achieved using bremsstrahlung photons from an 18 MV medical linear accelerator (linac) to bombard a Ra-226 target. A linac dose of 2800 Gy produced about 64 microCi of Ra-225, which decays to Ac-225. This result, while consistent with the theoretical calculations, is far too low to be of practical use. A more powerful linac is required that runs at a higher current, longer pulse length and higher frequency for practical production. This process could also lead to the reduction of the nuclear waste product Ra-226.

  11. Origin, quantities produced and ways of conditioning of special wastes in regional collection points

    Neider, R.

    1983-01-01

    Radioactive substances to be collected at regional collecting points are mostly related to the radionuclides H-3, Ra-226 and Th-232. These special wastes form a particular group of wastes including such solid wastes which do not contain volatile radionuclides yet cannot, for other reasons, be conditioned in accordance with the old Asse qualifications. (orig./DG) [de

  12. Distribution of Ra-226 in the Ross Sea, Antarctica

    Bettoli, M.G.; Cantelli, L.; Queirazza, G.; Roveri, M.; Tositti, L.; Tubertini, O.; Valcher, S.

    1996-01-01

    An improved procedure for the determination of Rn-222 and Ra-226 in seawater developed for easier on-board operations is presented. Data on the radioactive disequilibrium between the mentioned radionuclides as directly determined in the field can be greatly helpful in the study of the gas-exchange processes at the air-sea interface, especially as far as the Antarctic Ocean is concerned. The method employed has been preliminary tested in laboratory on a set of seawater samples collected in the Ross Sea and Ra-226 data collected are discussed and compared to literature data. (UK)

  13. Simultaneous determination of Ra-226, Ra-228 and Pb-210 using a successive coprecipitations techniques

    Vilhena Schayer Sabino, C. de; Kastner, S.M.S.; Amaral, A.M.

    1990-01-01

    Several techniques for determination of Ra-226, Ra228 and Pb-210. were developed and used in routine at CDTN in the laboratories of radiochemistry. The matrixes were: water and industrial wastes. Some problems of these techniques were the time spent for analyses and chemical separations, interferents, among others. Now-a-days the method in routine developed here is the one of successive coprecipitations, followed α and β countings of the Ra-226 and Ra-228 daughters. This method is based on coprecipitation, purification of barium radium sulfate with EDTA in acetic solution. Lead is dissolved, radium remains precipitated and suffers a new purification and the time for growing of their daughters is waited to be performed the simultaneous α and β countings for Ra-226 and Ra-228 determination. Pb-210 is analyzed in the floating of the first purification with a carrier of bismuth, and the time for Bi-210 growing is waited. Then it is precipitated as hydroxid, purified as phosphate and the β counting of Bi-210 is done. (author) [pt

  14. The Distributions of the Radionuclides Ra-226, Th-232 and K-40 in Various Parts of The Alfalfa Plant

    Salahel Din, K.; Harb, S.; Abbady, A.; Saad, N.

    2011-01-01

    The distribution of naturally occurring Ra-226, Th-232 and K-40 in different part of alfalfa plant from two different soils of Qena (South Valley University and Qena governorate farms) was studied under natural field conditions. Sixty two samples (alfalfa plant and its soil) were taken from nine sites inside farms. The samples were analyzed for their Ra-226, Th-232 and K-40 activity concentrations using gamma ray spectrometer consists of 3 x 3 NaI (Tl). The daily intakes of these radioisotopes by calves, milking cattle and sheep were calculated by multiplying concentrations in alfalfa and the daily consumption rates of these plants.

  15. A theoretical model for the production of Ac-225 for cancer therapy by photon-induced transmutation of Ra-226.

    Melville, G; Fan Liu, Sau; Allen, B J

    2006-09-01

    Radium needles that were once implanted into tumours as a cancer treatment are now obsolete and constitute a radioactive waste problem, as their half-life is 1600 years. We are investigating the reduction of radium by transmutation on a small scale by bombarding Ra-226 with high-energy photons from a medical linear accelerator (linac) to produce Ra-225, which subsequently decays to Ac-225, which can be used as a generator to produce Bi-213 for use in 'targeted alpha therapy' for cancer. This paper examines the possibility of producing Ac-225 with a linac using an accurate theoretical model in which the bremsstrahlung photon spectrum at 18 MV linac electron energy is convoluted with the corresponding photonuclear cross sections of Ra-226. The total integrated yield can then be obtained and is compared with a computer simulation. This study shows that at 18 MV, the photonuclear reaction on Ra-226 can produce low activities of Ac-225 with a linac. However, a high power linac with high current, pulse length and frequency is needed to produce practical amounts of Ac-225 and a useful reduction of Ra-226.

  16. Estuarine geochemistry of 224Ra, 226Ra, and 222Rn

    Elsinger, R.J.

    1982-01-01

    Desorption from river borne sediments is the most likely source of the excess 226 Ra. Laboratory mixing experiments on Pee Dee River sediments show an increase in 226 Ra desorption with increasing salinities with maximum desorption occurring at or above 20 0 /oo salinity. Desorption and diffusion are the sources for 226 Ra in the estuarine systems. In Winyah Bay the 228 Ra/ 226 Ra activity ratio does not change significantly with salinity, averaging around 1.4, indicating desorption as the major source of 228 Ra. In the Yangtze River the 228 Ra/ 226 Ra activity ratio is constant (approx.1.90) until increasing linearly above 16 0 /oo. A diffusive flux from regeneration by 232 Th decay in shelf sediments is the source of the increase. In Delaware Bay 228 Ra increases faster than 226 Ra in the less than or equal to22 0 /oo water, indicating a source in addition to desorption. The increase can be balanced by a 0.33 dpm/cm 2 -year flux over the upper part of the Bay where fine grained sediments predominate. 224 Ra behavior is controlled by its 3.64 day half-life. In Winyah Bay a flux of around 0.4 dpm/cm 2 -day is necessary to support the standing crop of non-desorbed 224 Ra in the water column. In Delaware Bay the nearly constant 224 Ra in concentration over the 2.5 0 /oo to 12 0 /oo salinity range are maintained by regeneration from 228 Th in the turbidity maximum zones and diffusion from bottom sediments. Water leaving on ebb tide from a salt marsh on Delaware Bay had increases in all three radium isotopes ( 224 Ra > 228 Ra > 226 Ra) compared to water coming in on the flood tide. Excess 222 Rn concentrations in a fresh water section of the Pee Dee River show a decreasing downstream gradient. Using these gradients to determine evasion rates, stagnant film thicknesses range from 21μ to 62μ

  17. Conditioning of Radium-226 sources in Cuba

    Benitez Navarro, Juan Carlos; Salgado Mojena, Mercedes; Gonzalez Rodriguez, Niurka; Castillo Gomez, Rafael; Berdellans Escobar, Ania; Otero Cabrera, Lazaro

    2011-01-01

    Abstract The production and use of Ra-226 sealed sources was internationally recommended to be halted for health and safety reasons. Consequently, all Ra-226 sources in Cuba were collected, characterized and conditioned. The paper describes the safety and operational aspects related to the Ra-226 conditioning. For this, a Special Permission was granted by the Regulatory Body, as required. A radiological assessment, a safety report as well as an emergency plan were prepared and approved before the operations. The work was accomplished with due reliability following an established comprehensive Quality Management System. As a result of these operations, 188.5 GBq of Ra-226, contained in different types of radiation sources (brachytherapy needles and tubes, standard sources for calibration, etc.) were encapsulated and conditioned. The capsules with the sources were conditioned in a retrievable form within fi ve waste packages intended for long term storage.(author)

  18. Measurement of Ra-226 in building materials, with a Na I (Tl) scintillation counter

    Vallejo, L.R.; Fuenteseca, J.W.; Rivera, C.A.; Aros, F.H.

    1992-01-01

    Ra-226 concentration in building materials is determined using gamma-ray spectrometry. Ra-226 contained in sundry materials employed in the construction of dwelling houses and public buildings in Antofagasta city is determined by counting the Pb-214 peaks at 295 KeV and 352 keV, and the Bi-214 peak at 609 keV recorded by means of a 7.5-cm Nal (TI) scintillation counter. (author)

  19. Measurements of Ra-226 content of water and drinks in West Germany

    Glaum, F.; Schastok, J.

    1986-01-01

    The contamination of the population by Ra 226 in water and drinks can be excluded as a potential source of danger. Average values in pCi/litre: Mineral water - 1.17, spa water - 2.55, beer - 0.57, wine - 0.92, milk - 0.08, tapwater - 0.11, waste water a) incoming - 0.22 b) outgoing - 0.14, activation basin - 1.2. The whole body equivalent doses and annual activity supply for an intake of 440 litres/annum to be expected are: Mineral water - 1.6x10 -4 Sv/a, 5.1x10 -10 Ci/a, spa water - 3.5x10 -4 Sv/a, 1.1x10 -9 Ci/a, beer - 7.8x10 -5 Sv/a, 2.5x10 -10 Ci/a, wine - 1.3x10 -4 Sv/a, 4.0x10 -10 Ci/a, milk - 1.1x10 -5 Sv/a, 3.5x10 -11 Ci/a, tapwater - 1.5x10 -5 Sv/a, 4.8x10 -4 Ci/a. (HP) [de

  20. Efficiency of Cleanup of Ra-226 Contaminated Gravel Assayed by LSC and TL Dosimetry

    Mamoon, A.; Abulfaraj, W.H.; Kamal, S.M.; Sohsah, M.A.

    1999-01-01

    The present study concerns itself with decontamination of gravel that had been contaminated with Ra-226 from natural origins. Aqueous solutions of different compositions including water, and various concentrations of CaCl 2 and BaCl 2 were used to leach the contaminated gravel. The leaching experiments were carried out in glass columns. In some leaching experiments a sample of a common brand of sandy soil (fine sand with traces of silt )was placed below the gravel to test the binding capacity (sorption) of this soil for the leached Ra-226

  1. Report on the intercomparison run IAEA-313 Ra-226, Th and U in stream sediment

    Strachnov, V.; Valkovic, V.; Zeisler, R.; Dekner, R.

    1991-01-01

    This report contains the results of the intercomparison IAEA-313 on the determination of uranium, thorium and Ra-226 in two stream sediments from Indonesia. The participants included 36 laboratories located in 18 countries, and statistical evaluation of their data yield recommended values for these elements. The elements, their recommended values and confidence intervals are: Ra-226, 343 Bq/kg (307-379); Th, 77.1 microg/g (74.8-79.4); U, 18.2 microg/g (17.0-19.3). Tabs

  2. Report on the intercomparison run IAEA-312 Ra-226, Th and U in soil

    Strachnov, V.; Valkovic, V.; Zeisler, R.; Dekner, R.

    1991-01-01

    This report contains the results of the intercomparison IAEA-312 on the determination of uranium, thorium and Ra-226 in an Indonesian soil sample. The participants included 39 laboratories located in 17 countries, and statistical evaluation of their data yield recommended values for these elements. The elements, their recommended values and confidence intervals are: Ra-226, 269 Bq/kg (250-287); Th, 91.4 microg/g (81.3-101.5); U, 16.5 microg/g (15.7-17.4). Tabs

  3. Distribution of Pa-231 and Ra-226 in rock. An indicator of rock matrix diffusion

    Saarinen, L.; Suksi, J.

    1995-01-01

    Distribution of Ra-226 and Pa-231 in rock has been studied to find signatures that may be attributed to diffusion. The idea of studying these nuclides originated from the need to obtain interpretative support to the findings of U movement in rock. Concentration profiles of Ra-226 and Pa-231 with other U series nuclides were measured across the secondary U accumulations observed in altered rock close to a fracture in the vicinity of U deposit, and in a radioactivity anomaly. (27 refs., 10 figs., 2 tabs.)

  4. Ra-226, Pb-210, and Po-210 in the Black Forest

    Schuettelkopf, H.; Kiefer, H.

    1981-01-01

    By measuring Pb-210, Po-210 and Ra 226 in air, water, ground, plants, and food samples the concentration ranges of the radionuclide and the transfer factor important for the calculation of the ingestion dose of man were determined. Po 210 was found to have the lowest radiotoxicity. The highest Po-210 concentrations were found in protein-containing food. (DG) [de

  5. Risk assessment of human exposure to Ra-226 in oil produced water from the Bakken Shale.

    Torres, Luisa; Yadav, Om Prakash; Khan, Eakalak

    2018-06-01

    Unconventional oil production in North Dakota (ND) and other states in the United States uses large amounts of water for hydraulic fracturing to stimulate oil flow. Most of the water used returns to the surface as produced water (PW) containing different constituents. Some of these contents are total dissolved solids and radionuclides. The most predominant radionuclide in PW is radium-226 (Ra-226) of which level depends on several factors including the content of certain cations. A multivariate regression model was developed to predict Ra-226 in PW from the Bakken Shale based on the levels of barium, strontium, and calcium. The simulated Ra-226 activity concentration in PW was 535 pCi/L supporting extremely limited actual data based on three PW samples from the Bakken (527, 816, and 1210 pCi/L). The simulated activity concentration was further analyzed by studying its impact in the event of a PW spill reaching a surface water body that provides drinking water, irrigation water for crops, and recreational fishing. Using food transfer factors found in the literature, the final annual effective dose rate for an adult in ND was estimated. The global average annual effective dose rate via food and drinking water is 0.30 mSv, while the predicted dose rate in this study was 0.49 mSv indicating that there is potential risk to human health in ND due to Ra-226 in PW spills. This predicted dose rate is considered the best case scenario as it is based on the simulated Ra-226 activity concentration in PW of 535 pCi/L which is close to the low end actual activity concentration of 527 pCi/L. Copyright © 2018 Elsevier B.V. All rights reserved.

  6. Field measurements of radon exhalation and Ra-226 content in soil using the can-technique

    Hafez, A.F.; El-Khatib, A.M.; Moharram, B.M.; Kotb, M.A.; Abdel-Naby, A.

    1991-01-01

    CR-39 and LR-115 plastic nuclear track detectors in the can-technique have been employed in the field measurements of radon exhalation, Ra-226 and U-238 content in dry-soil air at numerous regions in Sudan (the Blue and White Nile and Mogran regions). Measurements gave an average radon exhalation from the soil to the atmosphere and Ra-226 content of (23.4±2.60) kBq.m -2 and (123±13.65) Bq.kg -1 respectively. A polyethylene permeable memebrane cover was used to eliminate the contribution of thoron activity inside the can. Assuming a radioactive equilibrium between the U-series, the average U-238 content in the soil was found to be (9.92±1.01) ppm. This survey may be used for uranium prospection in soil. (orig.) [de

  7. RA-226 concentration in water samples near uranium mines and in marine fishes

    Porntepkasemsan, B.

    1987-11-01

    Radium-226 and calcium were measured in water samples from the vicinity of three uranium mines and in fish samples collected from Puget sound, Washington State. The radium content of the samples were below the maximum permissible concentration 3 pCi/L for drinking water recommended by the Public Health Service and U.S. Environmental Protection Agency. The mean value of Ra-226 in water was 0.428 pCi/L and ranged from 0.043 to 1.552 pCi/L, whereas calcium content ranged from 3.0 to 190.0 mg/L. Ra-226 concentrations and calcium content in whole fish were 0.833-20.328 pCi/kg wet wt. and 114.1-259.3 mg/g ash, respectively. Results of the study indicated that Ra-226 concentration in water was correlated with calcium concentration but that this correlation was not observed in fish sample except English sole

  8. The determination of Pb-210 and Ra-226 in lake sediments and dating applications

    Farid, M.; El-Daoushy, A.F.

    1978-04-01

    The natural radioactive isotopes Pb-210 and Ra-226 were measured in two sediment cores. The Pb-210 was determined by α-detection of its grand-daughter product Po-210, using the isotope dilution technique and a surface barrier detector. Some technical improvements in the polonium extraction were achieved. The radon emanation technique was used for the determination of Ra-226. The α-activity of Rn-222 was measured using an ionization chamber with an improved filling system, which allows both low level measurements and counter calibration with standard active samples. The memory effect due to adsorption of Rn-222 on the counter walls is studied. The accumulation rates are calculated from the unsupported Pb-210. The results from one core, Gillfjaerden, are in good agreement with some studies of the reservoir effect using C-14. The data from the other core, Lake Vaexjoesjoen, indicated an irregularity in the Pb-210 profile. Results from other studies on Lake Vaexjoesjoen showed a similar propensity

  9. Determination of Ra-226 and Th-232 in samples of natural phosphates, industrial gypsums and surface soils by gamma spectrometry

    Pessenda, L.C.R.; Nascimento Filho, V.F. do; Nadai, E.A. de; Barros Ferraz, E.S. de; Sao Paulo Univ., Piracicaba

    1988-01-01

    The natural radioactivity in Ra-226 and Th-232 in samples of natural phosphates, industrial gypsums (phosphogypsums) and surface soils of different regions was measured by γ-ray spectrometry. The majority of phosphates and gypsums examined showed significantly higher values than soils, mainly in relation to Ra-226 activity. The activity ranges found for phosphates, gypsums and soils were: 79.1 - 3180 Bq/kg, 56.3 - 986.6 Bq/kg, 8.8 - 54.3 Bq/kg for Ra-226 and 33.6 - 1450.3 Bq/kg; 17.4 - 130,1 Bq/kg, 9.8 - 108.9 Bq/kg for Th-232, respectively. (author) [pt

  10. Absorption and removal of Ra-226, Pb-210 and Po-210 by humans and the resulting radiation exposure

    Gloebel, B.; Berlich, J.; Andres, C.

    1985-01-01

    In over 400 samples (food, water, air, stools and urine), the concentration of Ra-226, Pb-210 and Po-210 was measured. The daily intake for the three nuclides is: Ra-226: 30 mBq; Pb-210: 150 mBq; Po-210: 150 mBq. The table shows intake of individual food and drinking items as well as air. In all but the kidney samples, Pb and Po were present in radioactive equilibrium. The contribution of each radionuclide to radiation exposure is indicated. (orig./HP) [de

  11. Evaluation of the received dose by the Ra-226 incorporation due to the consumption of ground waters in Cuba

    Zerquera, T.J.; Prendes A, M.

    1996-01-01

    Due to the good solubility of radium compounds in the earth core, concentrations of Ra-226 in ground water may be significant. Some countries, like France and Finland, have reported Ra-226 concentrations in ground water up to 2700 and 5300 mBq/L, respectively. Due to to these reasons, the control of the concentrations of Ra-226 in water for human consumption became a practice in various countries. Sampling and analysis of Ra-226 in water from the principal springs and sources in Cuba have been organized since 1992, taking into account the volumes and primary features of each source. Radium-226 concentrations in analyzed waters are in the range of 26-144 mBq/L. These concentrations correspond to values reported in the literature for sources in other countries. Committed dose for water consumption in a year are in the order of nano Sievert. Determined concentrations are below the values established by corresponding Cuban Standard and no restriction have been recommended. (authors). 5 refs., 2 figs

  12. Seasonal variations in 228Ra/226Ra ratio within coastal waters of the Sea of Japan: implications for water circulation patterns in coastal areas

    Inoue, M.; Tanaka, K.; Watanabe, S.; Kofuji, H.; Yamamoto, M.; Komura, K.

    2006-01-01

    In this study, low-background γ-spectrometry was used to determine the 228 Ra/ 226 Ra ratio of 131 coastal water samples from various environments around Honshu Island, Japan (mainly around Noto Peninsula) at 1-3 month intervals from April 2003 until September 2005. Spatial variation in 228 Ra/ 226 Ra ratios was also assessed by analyzing 34 coastal water samples from five areas within the Sea of Japan during May and June 2004. The 228 Ra/ 226 Ra ratio of coastal water from all sites around Noto Peninsula shows seasonal variation, with minimum values during summer ( 228 Ra/ 226 Ra = 0.7) and maximum values during autumn-winter ( 228 Ra/ 226 Ra = 1.7-2). This seasonal variation is similar to that recorded for coastal water between Tsushima Strait and Noto Peninsula. The measured lateral variation in 228 Ra/ 226 Ra ratios within coastal water between Tsushima Strait and Noto Peninsula is only minor (0.5-0.7; May-June 2004). Coastal waters from two other sites (Pacific shore and Tsugaru Strait, north Honshu) show no clear seasonal variation in 228 Ra/ 226 Ra ratio. These measured variations in 228 Ra/ 226 Ra ratio, especially the temporal variations, have important implications for seasonal changes in patterns of coastal water circulation within the Sea of Japan

  13. 226Ra, 228Ra and 228Ra/226Ra in surface marine sediment of Malaysia

    Mei-Wo Yii; Zal Uyun Wan-Mahmood

    2013-01-01

    Surface sediment samples were collected at the West (east coast and west coast of Peninsular Malaysia) and East (Sabah and Sarawak) Malaysia in several expeditions within August 2003 until June 2008 for determining the level of natural radium isotopes. Activity concentrations of 226 Ra and 228 Ra in surface marine sediment at 176 sampling stations were measured. The activity concentrations of both radionuclides in Malaysia (East and West Malaysia) display varied with the range from 9 to 158 Bq/kg dry wt. and 13 to 104 Bq/kg dry wt., respectively. Meanwhile, the ratio distributions of 228 Ra/ 226 Ra were ranged from 0.62 to 3.75. This indicated that the ratios were slightly high at west coast of Peninsular Malaysia compared to other regions (east coast of Peninsular Malaysia, Sabah and Sarawak). The variation of activity concentrations of 226 Ra and 228 Ra and its ratios were also supported by the statistical analyses of one-way ANOVA and t test at 95 % confidence level, whereby there were proved that the measured values were different between the regions. These different were strictly related to their half-life, potential input sources (included their parents, 238 U and 232 Th), parent's characteristic, the geological setting/formation of the study area, environment origin and behavior. (author)

  14. Simultaneous determination of Ra-226, natural uranium and natural thorium by gamma-ray spectrometry INa(Ti), in solid samples.; Determinacion de U (Natural), Th (Natural) y Ra-226 en diversos materiales, mediante espectrometria con INa (TI)

    Salvador, S.; Navarro, T.; Alvarez, A.

    1991-07-01

    A method has been developed to determine activities of Ra-226, natural uranium and natural thorium by gamma-ray spectrometry. The measurement system has been calibrated using standards specially prepared at the laboratory. It is necessary to assume secular equilibrium in the samples, between Ra-226 and Th-232 and its daughters nuclides, and between U-238 and its immediate daughter Th-234, as the photo peaks measured are those of the daughters. The results obtained indicate that this method can of ter replace the radiochemical techniques used to measure activities in this type of sample. The method has been successfully used to determine these natural isotopes in samples from uranium mills. (Author) 9 refs.

  15. Leachability of Ra-226 from uranium mill tailings consolidated with naturally occuring materials and/or cement. Pt. 2

    Nathwani, J.S.; Phillips, C.R.

    1980-01-01

    The leaching of Ra-226 from U mill tailings consolidated with cement and cement plus clay and/or peat may be described by a plane source diffusion model or a simultaneous first order reaction and diffusion model. A useful quantitative measure of the effectiveness of the consolidation process is the magnitude of the effective diffusion coefficient relative to that of the unconsolidated tailings material. The lowest effective diffusion coefficient upon consolidation was for consolidation with cement and peat. (orig.)

  16. Pre-operational monitoring program of Ra-226 in biological material in uranium mining and milling areas

    Souza Pereira, Wagner de; Azevedo Py Junior, Delcy de; Kelecom, Alphonse; Iatesta, Antonio

    2008-01-01

    The environmental licensing processes of 'Santa Quiteria' uranium mining and milling unit are being carried out nowadays. The pre-operational radiological environmental monitoring program is part of those processes, which has the objective of determining the background for further comparisons and evaluation of radiological environmental impact of the operation unit. This work shows the results of Ra-226 determination in the most consumed farm products of the region, which are black beans, corn and milk. These data are compared with data available in the literature. Measurement results of Ra-226 in black beans vary from 3.3 x 10 -2 Bq/Kg to 9.1 x 10 -2 Bq/Kg; in corn, the results vary from 8.0 x 10 -3 Bq/Kg to 4.6 x 10 -2 Bq/Kg; in milk the results vary from 1.0 x 10 -3 Bq/Kg to 7.0 x 10 -3 Bq/Kg that represents the smallest variation range. All of these results are in good agreement with literature reported data. (author)

  17. Simultaneous determination of RA-226, natural uranium and natural thorioum by gamma-ray spectrometry INa(Tl) in solid samples

    Salvador, S.; Navarro, T.; Alvarez, A.

    1990-01-01

    A method has been described to determine activities of Ra-226, natural uranium, and natural thorium, by gamma-ray spectrometry. The system was calibrated for efficiency by using synthetic calibrated standards. It is necessary, in the samples, to assume secular equilibrium between Ra-226 and Th-232 and its daughters nuclides, and U-238 and its immediate daughter Th-234, because the photopeaks measured are from these dsaugthers. Our results indicate that a non destructive gamma spectrometric method can ofter replace the radiochemical techniques used in measuring radiactivities in this type of samples. (Author). 9 refs

  18. Influences of liming on the soil-plant transfer of Ra-226 from acid soils field experiments

    Eriksson, Aa.

    1985-01-01

    The effects of liming of the plough layer in the early sixties on the contents of exchangeable Ca and Ra-226 in soil, and on the contents of Ca and Ra in the crops in the early eighties have been investigated. It was found that liming, while increasing the amounts of Ca, reduced the amounts of Ra and the ratio Ra/Ca exchangeable in soil. Liming influenced the plant upake of Ra more for the vegetative than for the generative parts of the grain crops. However, the reduction of the Ra/Ca-ratio in the former was not as effective as in the soil. In the grain it was uncertain. The difference can, however, be explained by the fact that the minerals in straw and grain are more or less taken from different layers of the soil profile. The crop is more dependant on the plough layer during the early development than later, when grain is developed

  19. Micro-extraction procedures for the determination of Ra-226 in well waters by SF-ICP-MS

    Lariviere, D.; Epov, V.N.; Reiber, K.M.; Cornett, R.J.; Evans, R.D.

    2005-01-01

    The radium-226 (t 1/2 = 1622 years) content of highly alkaline well water collected from the United Arab Emirates (UAE) was measured by double focusing sector-field inductively coupled plasma-mass spectrometry (SF-ICP-MS) after separation of the radium from other alkaline earth elements using a newly developed procedure. The results were comparable with those obtained by α-spectrometry for samples with concentrations ranging from 6.75 to 459 pg/L (0.25 to 17 Bq/L). Instrumental sensitivity on matrix-free samples was compared for two sample introduction systems, i.e. an Apex-Q high sensitivity system and a concentric nebulizer. A 12-fold improvement in sensitivity (instrumental detection limit = 1.5 pg/L or 55 mBq/L) was found when the Apex-Q system was used. Two chromatographic methods were tested for the sequential separation of the alkaline earth elements contained in the well water samples in order to reduce matrix and polyatomic interference effects. Optimal elution parameters were determined and used for the separation and pre-concentration of Ra-226 in those samples. A method detection limit of 0.189 pg/L (7 mBq/L), which corresponds to a mass of 0.38 fg of Ra-226 in the sample, was achieved. Only 2 mL of sample is necessary when a combination of 50 W-X8 and Sr*Spec resin, which are reusable, are utilized for the separation. This new analytical protocol significantly reduces sample preparation time resulting in a throughput rate of approximately 20 samples in only 8 h; faster than the other published extraction procedures

  20. Seasonal variation of 228Ra/226Ra ratio in seaweed: implications for water circulation patterns in coastal areas of the Noto Peninsula, Japan

    Inoue, M.; Kofuji, H.; Yamamoto, M.; Komura, K.

    2005-01-01

    To examine water circulation patterns of coastal water, 72 seaweed (Sargasso) samples and 27 coastal water samples were collected from coastal areas of the Noto Peninsula, Japan, during the period from December 1998 to June 2002. The 228 Ra and 226 Ra activities of those samples were measured by low-background γ-ray spectrometry. There was a wide range of activities of 228 Ra (0.5-2 Bq/kg-fresh) and 226 Ra (0.5-1.2 Bq/kg-fresh) in the Sargasso samples. The 228 Ra/ 226 Ra activity ratio of Sargasso samples exhibited seasonal variation with minimum values in June ( 228 Ra/ 226 Ra = ∼1) and maximum values in December (1.5-2.5), which was mainly governed by changes in 228 Ra activity. It is also notable that the seasonal variation of the 228 Ra/ 226 Ra ratio of Sargasso is in approximate agreement with that of the ambient coastal water. Sargasso samples appear to have retained the 228 Ra/ 226 Ra ratio of the ambient coastal waters, and the temporal variations in that ratio provide insight into seasonal changes in water circulation in the Noto Peninsula coastal area

  1. Development of a methodology for the detection of Ra226 in large volumes of water by gamma spectrometry; modification and validation of the method for detection and quantification of Ra226 in small volumes of water by alpha spectrometry, used by the Centro de Investigacion en Ciencias Atomicas, Nucleares y Moleculares (CICANUM, UCR)

    Molina Porras, Arnold

    2011-01-01

    The test method has been validated for quantifying the specific activity of Ra 226 in water alpha spectrometry. The CICANUM has used this method as part of the proposed harmonization of methods ARCAL (IAEA). The method is based on a first separation and preconcentration of Ra 226 by coprecipitation and subsequent MnO 2 micro precipitation as Ba (Ra) SO 4 . Samples were prepared and then was performed the counting by alpha spectrometry. A methodology of radio sampling for large volumes of water was tested in parallel, using acrylic fibers impregnated with manganese oxide (IV) to determine the amount of Ra 226 present by gamma spectrometry. Small-scale tests, have determined that the best way to prepare the fiber is the reference method found in the literature and using the oven at 60 degrees Celsius. (author) [es

  2. Quality control of Ir-192, Cs-137 and Ra-226 sources for use in brachytherapy

    Oyrzun Cortes, C.H.; Palma D, A.M.; Penaloza C, H.; Tomicic, M.

    1996-01-01

    In order to establish a certain degree of reliability in the use and managing of radioactive material in brachytherapy, a minimal quality control to each source was implemented. The purpose was to estimate the degree of radioactive leak, resistance to the mechanic traction and stress of use. Through a physical control of the radioactive material (a simple dip test and using a photon scanner or auto-radiography) the minimal conditions that guarantee safe use are established. This information is transmitted to a calibration laboratory for certification in exposure rate and/or activity. Systematic use of these tests, enables discovery of radioactive material leakage due to faults in the seal. (author)

  3. Quality control of Ir-192, Cs-137 and Ra-226 sources for use in brachytherapy

    Oyrzun Cortes, C H; Palma D, A M; Penaloza C, H; Tomicic, M [Comision Chilena de Energia Nuclear, Santiago (Chile)

    1996-08-01

    In order to establish a certain degree of reliability in the use and managing of radioactive material in brachytherapy, a minimal quality control to each source was implemented. The purpose was to estimate the degree of radioactive leak, resistance to the mechanic traction and stress of use. Through a physical control of the radioactive material (a simple dip test and using a photon scanner or auto-radiography) the minimal conditions that guarantee safe use are established. This information is transmitted to a calibration laboratory for certification in exposure rate and/or activity. Systematic use of these tests, enables discovery of radioactive material leakage due to faults in the seal. (author).

  4. Simultaneous determination of Ra-226, natural uranium and natural thorium by gamma-ray spectrometry INa(Ti), in solid samples

    Salvador, S.; Navarro, T.; Alvarez, A.

    1991-01-01

    A method has been developed to determine activities of Ra-226, natural uranium and natural thorium by gamma-ray spectrometry. The measurement system has been calibrated using standards specially prepared at the laboratory. It is necessary to assume secular equilibrium in the samples, between Ra-226 and Th-232 and its daughters nuclides, and between U-238 and its immediate daughter Th-234, as the photo peaks measured are those of the daughters. The results obtained indicate that this method can of ter replace the radiochemical techniques used to measure activities in this type of sample. The method has been successfully used to determine these natural isotopes in samples from uranium mills. (Author) 9 refs

  5. Estimating calibration equations for predicting Ra-226 soil concentrations using RTRAK in-situ detectors at the Ambrosia Lake, New Mexico, Umtra site

    Gilbert, R. O.; Meyer, H. R.; Miller, M. L.; Begley, C.

    1988-06-01

    This report describes a field study conducted at the Ambrosia Lake, New Mexico, UMTRA site to obtain data for calibrating the RTRAK Sodium Iodide (NaI) detectors for estimating concentrations of Ra-226 in surface soil. The statistical analyses indicate that the data are useful for estimating the calibration equations. Several statistical models are used to evaluate which model is best as a basis for the calibration equations. A procedure is provided for using the estimated calibration equations and extensive RTRAK measurements to estimate the average Ra-226 concentration on 100-m 2 land areas to determine whether additional remedial action is needed. The UMTRA Project office proposes to use the RTRAK for cleanup verification of surface Ra-226 contamination. The system enables 100% coverage of areas having undergone remedial action. The sensitivity of the system enables verification at less than 5 pCi/g averaged over 100 m 2 , as specified by the Environmental Protection Agency (EPA) standards (40 CFR Part 192). This analysis demonstrates RTRAK's ability to meet reasonable standards of statistical accuracy, using commonly accepted procedures. 5 refs., 8 figs., 1 tab

  6. Studies of transport pathways of Th, U, rare earths, Ra-228, and Ra-226 from soil to plants and farm animals: Final progress report, 1983-1988

    Linsalata, P

    1988-07-01

    This report consists of three parts. Part 1 discusses a field study conducted in an area of enhanced, natural radioactivity to assess the soil to edible vegetable concentration ratios (CR = concentration in dry vegetable/concentration in dry soil) of Th-232, Th-230, Ra-226, Ra-228, and the light rare earth elements (REE's), La, Ce, and Nd. Twenty-eight soil, and approximately 42 vegetable samples consisting of relatively equal numbers of seven varieties, were obtained from 11 farms on the Pocos de Caldas Plateau in the state of Minas Gerais, Brazil. This region is the site of a major natural analogue study to assess the mobilization and retardation processes affecting thorium and the REE's at the Morro do Ferro ore body, and uranium series radionuclides at the Osamu Utsumi open pit uranium mine. Thorium (IV) serves as a chemical analogue for quadrivalent plutonium, the light REE's (III) as chemical analogues for trivalent americium and curium, and uranium (VI) as an analogue for transuranics with stable oxidation states above IV, e.g., Pu(VI). Part 2 includes our final measurement results for naturally occurring light rare earth elements (REE's include La, Ce, Nd, and SM), U-series and Th-series radionuclides in adult farm animal tissues, feeds and soils. Our findings on soil-to-tissue concentration ratios (CR's) and the comparative behavior of these elements in farm animals raised under natural conditions by local farmers are presented. Part 3 summarizes our findings to date on the distribution and mobilization of Th-232, light rare earth elements (LREE), U-238 and Ra-228 in the MF basin. Estimates of first order, present day, mobilization rate constants resulting from ground water solubilization and seepage/stream transport are calculated using revised inventory estimates for the occurrence of these elements in the ore body and annual flux estimates for the transport of these elements away from the ore body. 151 refs., 20 figs., 40 tabs.

  7. Determination of natural radionuclides, U, Th-232, Ra-226, Ra-228, Pb-210 and K-40 in sediments from CananÉIa-Iguape System, Brazil

    Jesus, Gleyka J.D.; Chiozzini, Vitor G.; Saueia, Cátia H.R.; Nisti, Marcelo B.; Braga, Elisabete S.; Fávaro, Deborah I.T.; Universidade de São Paulo

    2017-01-01

    The Cananéia-Iguape estuarine-lagoon complex, located in the south of São Paulo State, Brazil, is a protected area recognized by UNESCO as part of the Biosphere Reserve, due to its importance as a natural ecosystem. However, along the years, the mining activities in the region affected the river basin, to such an extent that contamination was observed for As, Cu, Pb and Zn. Since the mining activities can also enhance the levels of natural radioactivity in the sediments, this study aimed to determine the activity concentration of the natural radionuclides (K-40, U, Ra-226, Pb-210, Th-232 and Ra-228) in 34 bottom sediments samples collected in the Cananéia-Iguape system. The samples were measured by gamma spectrometry, using a HPGe for the determination of K-40, Ra-226, Pb-210 and Ra-228. The concentration of U and Th-232 was determined by instrumental neutron activation analysis. The activity concentration of K-40 varied from 119 ± 17 to 522 ± 74 Bq kg"-"1; U-238 varied from 0.31 ± 0.05 to 5.8 ± 0.3 mg kg"-"1; Ra-226 varied from 3.7 ± 0.3 to 43.3 ± 1.5 Bq kg"-"1; Pb-210 varied from 5.8 ± 2.6 to 118 ± 12 Bq kg"-"1; Th-232 varied from 0.67 ± 0.02 to 16.6 ± 0.4 mg kg"-"1 and Ra-228 varied from 3.5 ± 0.6 to 64.9 ± 2.4 Bq kg"-"1. These results were compared with literature values for the region, indicating that they are the background of the region and no contamination was observed from NORM (Naturally Occurring Radioactive Material) industries. (author)

  8. Determination of concentration factors for Cs-137 and Ra-226 in the mullet species Chelon labrosus (Mugilidae) from the South Adriatic Sea

    Antovic, Ivanka [Department for Biochemical and Medical Sciences, State University of Novi Pazar, Vuka Karadzica bb, 36 300 Novi Pazar (Serbia); Antovic, Nevenka M., E-mail: nenaa@rc.pmf.ac.me [Faculty of Natural Sciences and Mathematics, University of Montenegro, Dzordza Vasingtona bb, 20 000 Podgorica (Montenegro)

    2011-07-15

    Concentration factors for Cs-137 and Ra-226 transfer from seawater, and dried sediment or mud with detritus, have been determined for whole, fresh weight, Chelon labrosus individuals and selected organs. Cesium was detected in 5 of 22 fish individuals, and its activity ranged from 1.0 to 1.6 Bq kg{sup -1}. Radium was detected in all fish, and ranged from 0.4 to 2.1 Bq kg{sup -1}, with an arithmetic mean of 1.0 Bq kg{sup -1}. In regards to fish organs, cesium activity concentration was highest in muscles (maximum - 3.7 Bq kg{sup -1}), while radium was highest in skeletons (maximum - 25 Bq kg{sup -1}). Among cesium concentration factors, those for muscles were the highest (from seawater - an average of 47, from sediment - an average of 3.3, from mud with detritus - an average of 0.8). Radium concentration factors were the highest for skeleton (from seawater - an average of 130, from sediment - an average of 1.8, from mud with detritus - an average of 1.5). Additionally, annual intake of cesium and radium by human adults consuming muscles of this fish species has been estimated to provide, in aggregate, an effective dose of about 4.1 {mu}Sv y{sup -1}. - Highlights: > Radionuclide transfer from seawater, sediment and mud with detritus. > Concentration factors for Cs-137 and Ra-226 in C. labrosus whole fish and organs. > Cs-137 concentration factors are highest for C. labrosus muscles. > Ra-226 concentration factors are highest for C. labrosus skeleton.

  9. Determination of concentration factors for Cs-137 and Ra-226 in the mullet species Chelon labrosus (Mugilidae) from the South Adriatic Sea

    Antovic, Ivanka; Antovic, Nevenka M.

    2011-01-01

    Concentration factors for Cs-137 and Ra-226 transfer from seawater, and dried sediment or mud with detritus, have been determined for whole, fresh weight, Chelon labrosus individuals and selected organs. Cesium was detected in 5 of 22 fish individuals, and its activity ranged from 1.0 to 1.6 Bq kg -1 . Radium was detected in all fish, and ranged from 0.4 to 2.1 Bq kg -1 , with an arithmetic mean of 1.0 Bq kg -1 . In regards to fish organs, cesium activity concentration was highest in muscles (maximum - 3.7 Bq kg -1 ), while radium was highest in skeletons (maximum - 25 Bq kg -1 ). Among cesium concentration factors, those for muscles were the highest (from seawater - an average of 47, from sediment - an average of 3.3, from mud with detritus - an average of 0.8). Radium concentration factors were the highest for skeleton (from seawater - an average of 130, from sediment - an average of 1.8, from mud with detritus - an average of 1.5). Additionally, annual intake of cesium and radium by human adults consuming muscles of this fish species has been estimated to provide, in aggregate, an effective dose of about 4.1 μSv y -1 . - Highlights: → Radionuclide transfer from seawater, sediment and mud with detritus. → Concentration factors for Cs-137 and Ra-226 in C. labrosus whole fish and organs. → Cs-137 concentration factors are highest for C. labrosus muscles. → Ra-226 concentration factors are highest for C. labrosus skeleton.

  10. Determination of natural radionuclides, U, Th-232, Ra-226, Ra-228, Pb-210 and K-40 in sediments from CananÉIa-Iguape System, Brazil

    Jesus, Gleyka J.D.; Chiozzini, Vitor G.; Saueia, Cátia H.R.; Nisti, Marcelo B.; Braga, Elisabete S.; Fávaro, Deborah I.T., E-mail: gjdjesus@ipen.br, E-mail: chsaueia@ipen.br, E-mail: mbnisti@ipen.br, E-mail: defavaro@ipen.br, E-mail: vitor.chio@usp.br, E-mail: edsbraga@usp.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil); Universidade de São Paulo (USP), SP (Brazil). Instituto Oceanográfico

    2017-07-01

    The Cananéia-Iguape estuarine-lagoon complex, located in the south of São Paulo State, Brazil, is a protected area recognized by UNESCO as part of the Biosphere Reserve, due to its importance as a natural ecosystem. However, along the years, the mining activities in the region affected the river basin, to such an extent that contamination was observed for As, Cu, Pb and Zn. Since the mining activities can also enhance the levels of natural radioactivity in the sediments, this study aimed to determine the activity concentration of the natural radionuclides (K-40, U, Ra-226, Pb-210, Th-232 and Ra-228) in 34 bottom sediments samples collected in the Cananéia-Iguape system. The samples were measured by gamma spectrometry, using a HPGe for the determination of K-40, Ra-226, Pb-210 and Ra-228. The concentration of U and Th-232 was determined by instrumental neutron activation analysis. The activity concentration of K-40 varied from 119 ± 17 to 522 ± 74 Bq kg{sup -1}; U-238 varied from 0.31 ± 0.05 to 5.8 ± 0.3 mg kg{sup -1}; Ra-226 varied from 3.7 ± 0.3 to 43.3 ± 1.5 Bq kg{sup -1}; Pb-210 varied from 5.8 ± 2.6 to 118 ± 12 Bq kg{sup -1}; Th-232 varied from 0.67 ± 0.02 to 16.6 ± 0.4 mg kg{sup -1} and Ra-228 varied from 3.5 ± 0.6 to 64.9 ± 2.4 Bq kg{sup -1}. These results were compared with literature values for the region, indicating that they are the background of the region and no contamination was observed from NORM (Naturally Occurring Radioactive Material) industries. (author)

  11. Determination of specific activities of U-238, Ra-226, Ra-228 e Th-228 in samples of mineral fertilizers with phosphorus

    Garcez, R.W.D.; Lopes, J.M.; Silva, A.X. da

    2016-01-01

    Samples were analyzed by gamma spectrometry mineral fertilizers with the HPGe detector and aid LabSOCS software for calculating the detection efficiency curve. Specific activities found for Pa-234m, Ra-226, Ra-228 and Th-228 in samples of phosphate fertilizers were 505 Bq.kg"-"1, 458 Bq.kg"-"1, 450 Bq.kg"-"1 and 394 Bq.kg"-"1, respectively. And for the NPK fertilizer samples were found average values of 390 Bq.kg"-"1, 252 Bq.kg"-"1, 280 Bq.kg"-"1 and 268 Bq.kg"-"1, respectively. (author)

  12. Estimation of Ra-226, Ra-228 and K-40 specific activities in fertilizer samples marketed in the Rio de Janeiro City

    Garcêz, R.W.D.; Lopes, J.M.; Silva, A. X. da, E-mail: rgarcez@nuclear.ufrj.br [Universidade Federal do Rio de Janeiro (LAASC/UFRJ), Rio de Janeiro, RJ (Brazil). Departamento de Engenharia Nuclear; Lima, M.A.F. [Universidade Federal Fluminense (LARA/UFF), Niterói, RJ (Brazil). Departeamento de Biologia

    2017-07-01

    The use of fertilizers is a common practice in agriculture and several samples have radionuclides in their composition. This content is natural but some samples may have high concentrations of these radionuclides and this represent a potential radiological risk for plants, animals and water. Therefore, the radiometric analyses of these compounds is important, and the aim of this paper is to determine the specific concentration of K-40, Ra-226 and Ra-228 in fertilizer samples available in market of Rio de Janeiro city and discussing the impacts to agricultural soils caused by this practice. Four types of fertilizer samples were analyzed: nitrogen, potash, phosphate and NPK. They were analyzed through gamma spectroscopy technique with a HPGe detector and with the LabSOCS software for the calculation of the efficiency curve. The specific activities of Ra-226 ranged from 1.48 to 597 Bq/kg, Ra-228 ranged from 2.66 to 832 Bq/kg and K-40 ranged from 16 to 13941 Bq/kg. All samples, except two of nitrogen fertilizer, presented the absorbed dose rate in air, at 1m above the ground level, higher than the estimated average global terrestrial radiation for soil (51 nGy/h) and the phosphate fertilizer samples presented the highest average absorbed dose rate: 532.5 nGy/h, which indicates a greater potential of environmental contamination. (author)

  13. Radium isotope (223Ra, 224Ra, 226Ra and 228Ra) distribution near Brazil's largest port, Paranaguá Bay, Brazil

    Dias, Thais H.; Oliveira, Joselene de; Sanders, Christian J.; Carvalho, Franciane; Sanders, Luciana M.; Machado, Eunice C.; Sá, Fabian

    2016-01-01

    This work investigates the 223 Ra, 224 Ra, 226 Ra and 228 Ra isotope distribution in river, estuarine waters and sediments of the Paranaguá Estuarine Complex (PEC). The stratification of the Ra isotopes along water columns indicate differing natural sources. In sediments, the radium isotope activities was inversely proportional to the particle size. The highest concentrations of 223 Ra, 224 Ra, 226 Ra and 228 Ra in the water column were found in the bottom more saline waters and towards the inner of the estuary. These relatively high concentrations towards the bottom of the estuary may be attributed to the influence of tidally driven groundwater source and desorption from particles at the maximum turbidity zone. The apparent river water ages from the radium isotope ratios, 223 Ra/ 224 Ra and 223 Ra/ 228 Ra, indicate that the principal rivers that flow into the estuary have residence times from between 6 and 11 days. - Highlights: • Radium isotope concentrations were evaluated along a large estuarine system. • The radioactivity level in river, estuary and sediments was within a normal range. • Spatial distributions of site specific radionuclides have differing activities and sources.

  14. Evaluation of the Ra-226 activity in public-consumption water in the Huarangal Valley using the radiochemical precipitation method as Ba(Ra)SO4

    Ysla C, M.A.

    1999-01-01

    Five radiochemical methods for Ra-226 determination in public-consumption river waters are developed in this work. Quantification of this radionuclide was conducted through high-resolution gamma spectrometry. These five methods are based on the precipitation of Ra-226 as Ba(Ra)SO 4 . The second of these methods has been considered the best due to its low cost, high radiochemical performance (83,53%) and lowest standard deviation (7,97). Using the second method (standardized method) it was determined that the activity present in a 32 L sample of water is 0,1526 Bq/L. Assuming that each person in Huarangal Valley consumes an average of 2 liters of water a day, we can estimate that this person consumes 111,398 Bq anally, a very low percentage compared to the limit activity reported in other parts of the world. Physicochemical analysis were also conducted in waters of the Chillon river; the results obtained are within the permissible limits established by the World Health Organization, the Institute of Technological, Industrial and Technical Regulation Research (ITINTEC), and the law for Waters of the Ministry of Agriculture. One can conclude, from the physicochemical analysis that have been conducted, that the waters of the Chillon river are fit for public consumption and do not present specific radio-sanitary risks for people living in the Huarangal valley

  15. Determination of Ra-226, Ra-228 and K-40 specific activities in samples of mineral fertilizer marketed in the Rio de Janeiro City

    Garcez, R. W. D.; Marques L, J.; Da Silva, A. X.

    2017-10-01

    The use a fertilizers ia a common practice in agriculture and several samples have radionuclides in their composition, this content is natural but some samples may have high concentrations of these radionuclides and this represent a potential radiological risk for plants, animals and water. Therefore the radiometric analyses these compounds is important and the main aim of this paper is to determine the specific concentration of K-40, Ra-226 and Ra-228 in fertilizer samples available in market of Rio de Janeiro city and discussing the impacts to agricultural soils caused by this practice. The analyzed fertilizer samples are of four types: nitrogen, potash, phosphate and NPK, they were analyzed using gamma spectroscopy with a Hp-Ge detector and with the LabSOCS software for the calculation of the efficiency curve. The specific activities of Ra-226 ranged from 1.48 Bq/kg to 597 Bq/kg, Ra-228 ranged from 2.66 Bq/kg to 832 Bq/kg and K-40 ranged from 16 Bq/kg to 13941 Bq/kg. All samples, except two nitrogen fertilizer samples, presented the absorbed dose rate in air at 1 m above the ground level higher than the estimated average global terrestrial radiation of 51 n Gy/h and the phosphate fertilizer samples presented the highest average absorbed dose rate of 532.5 n Gy/h, which indicates a greater potential of environmental contamination. But considering a dilution (1:1000) g of fertilizer in soil was found an average increase of 0.36 μSv/y at the annual outdoor effective dose while the annual average for the soil is of 63 μSv/y, so the risk to human health is minimum. (Author)

  16. Determination of specific activities of U-238, Ra-226, Ra-228 e Th-228 in samples of mineral fertilizers with phosphorus; Determinacao das atividades especificas de U-238, Ra-226, Ra-228 e Th-228 em amostras de fertilizantes minerais com fosforo

    Garcez, R.W.D.; Lopes, J.M.; Silva, A.X. da, E-mail: rgarcez@nuclear.ufrj.br [Coordenacao dos Programas de Pos-Graduacao em Engenharoa (COPPE/UFRJ), Rio de Janeiro, RJ (Brazil). Programa de Engenharia Nuclear; Domingues, A.M.; Lima, M.A.F. [Universidade Federal Fluminense (UFF),Niteroi, RJ (Brazil)

    2016-07-01

    Samples were analyzed by gamma spectrometry mineral fertilizers with the HPGe detector and aid LabSOCS software for calculating the detection efficiency curve. Specific activities found for Pa-234m, Ra-226, Ra-228 and Th-228 in samples of phosphate fertilizers were 505 Bq.kg{sup -1}, 458 Bq.kg{sup -1}, 450 Bq.kg{sup -1} and 394 Bq.kg{sup -1}, respectively. And for the NPK fertilizer samples were found average values of 390 Bq.kg{sup -1}, 252 Bq.kg{sup -1}, 280 Bq.kg{sup -1} and 268 Bq.kg{sup -1}, respectively. (author)

  17. Conditioning of alpha waste

    Halaszovich, S.; Gerontopoulos, P.; Hennart, D.; Ledebrink, F.W.; Loida, A.; Phillips, D.C.; Vandevoorde, N.

    1985-01-01

    The long life and high radiotoxicity of the alph-emitting transuranics in radioactive waste provide an incentive for the constant improvement of existing processes and waste forms or the development of new alternatives, to isolate them safely from the biosphere. In the following, five processes at differing stages of development are outlined, the products ranging between cement, glass and ceramics: a process developed by ALKEM for the cementation of waste from fuel element manufacture; a process to improve the quality of cement products containing Magnox hulls, under development at AERE Harwell; high-temperature slagging incineration, developed at SCK/CEN; embedding of waste in an alumosilicate-based ceramic, being developed at KfK; embedding of waste in a titanium dioxide-based ceramic, proposed by Agip

  18. Conditioning of alpha bearing wastes

    1991-01-01

    Alpha bearing wastes are generated during the reprocessing of spent fuel, mixed oxide fuel fabrication, decommissioning and other activities. The safe and effective management of these wastes is of particular importance owing to the radiotoxicity and long lived characteristics of certain transuranic (TRU) elements. The management of alpha bearing wastes involves a number of stages which include collection, characterization, segregation, treatment, conditioning, transport, storage and disposal. This report describes the currently available matrices and technologies for the conditioning of alpha wastes and relates them to their compatibility with the other stages of the waste management process. The selection of a specific immobilization process is dependent on the waste treatment state and the subsequent handling, transport, storage and disposal requirements. The overall objectives of immobilization are similar for all waste producers and processors, which are to produce: (a) Waste forms with sufficient mechanical, physical and chemical stability to satisfy all stages of handling, transport and storage (referred to as the short term requirements), and (b) Waste forms which will satisfy disposal requirements and inhibit the release of radionuclides to the biosphere (referred to as the long term requirements). Cement and bitumen processes have already been successfully applied to alpha waste conditioning on the industrial scale in many of the IAEA Member States. Cement systems based on BFS and pozzolanic cements have emerged as the principal encapsulation matrices for the full range of alpha bearing wastes. Alternative technologies, such as polymers and ceramics, are being developed for specific waste streams but are unlikely to meet widespread application owing to cost and process complexity. The merits of alpha waste conditioning are improved performance in transport, storage and disposal combined with enhanced public perception of waste management operations. These

  19. Conditioning and storage of spent sealed radium sources

    Cholerzynski, A.; Tomczak, W.

    2001-01-01

    In Poland sealed radioactive sources (SRS) are extensively used in medicine and in industry. There are mainly Co-60, Cs-137, lr-192 and also historical sources contain in Ra-226. The Radioactive Waste Management Department (ZDUOP) of the Institute of Atomic Energy at Swierk is the only organization licensed for the management, storage and disposal of radioactive waste in Poland. ZDUOP deals with all radioactive waste in the country. Storage and disposal of SRS is one of the most important part of its activity. Every year ZDUOP collects about 1000 spent SRS which total activity is near 600 GBq. Spent Ra-226 sources are a special case and therefore are required suitable procedures. Due to their production according to earlier standards and their undesirable characteristics, leakage of these sources is highly possible and practically observed. For this reason conditioning of radium sources needs strict requirements and quality assurance procedure to guarantee their safe storage for an extended period of time (e.g. 40-70 years). The National Radioactive Waste Repository is superficial type repository and considered as temporary storage site for long-lived waste. A storage facility for spent SRS has been properly prepared and licensed by the regulatory body. This facility consist of several concrete chambers which floor is lined stainless steel. The existing regulatory framework for sealed radioactive sources entered into force with issue of the Atomic Law in 1986

  20. Determination of concentration factors for Cs-137 and Ra-226 in the mullet species Chelon labrosus (Mugilidae) from the South Adriatic Sea.

    Antovic, Ivanka; Antovic, Nevenka M

    2011-07-01

    Concentration factors for Cs-137 and Ra-226 transfer from seawater, and dried sediment or mud with detritus, have been determined for whole, fresh weight, Chelon labrosus individuals and selected organs. Cesium was detected in 5 of 22 fish individuals, and its activity ranged from 1.0 to 1.6 Bq kg(-1). Radium was detected in all fish, and ranged from 0.4 to 2.1 Bq kg(-1), with an arithmetic mean of 1.0 Bq kg(-1). In regards to fish organs, cesium activity concentration was highest in muscles (maximum - 3.7 Bq kg(-1)), while radium was highest in skeletons (maximum - 25 Bq kg(-1)). Among cesium concentration factors, those for muscles were the highest (from seawater - an average of 47, from sediment - an average of 3.3, from mud with detritus - an average of 0.8). Radium concentration factors were the highest for skeleton (from seawater - an average of 130, from sediment - an average of 1.8, from mud with detritus - an average of 1.5). Additionally, annual intake of cesium and radium by human adults consuming muscles of this fish species has been estimated to provide, in aggregate, an effective dose of about 4.1 μSv y(-1). 2011 Elsevier Ltd. All rights reserved.

  1. The use of Pb-210/Ra-226 and Th-228/Ra-228 dis-equilibria in the ageing of otoliths of marine fish

    Smith, J.N.; Nelson, R.; Campana, S.E.

    1991-01-01

    Naturally-occurring isotopes of radium are ideally suited as tracers for chemical uptake in the calcified tissues of marine organisms since radium is a water soluble, bio-geochemical analogue for calcium. Assays designed to exploit this uptake mechanism can be used to determine the longevity of certain species of fish. Measurements of Pb-210/Ra-226 disequilibria in the otoliths of redfish have revealed that this species of fish can live to ages in excess of 75 years in coastal waters off Nova Scotia, Canada. Measurements of the Th-228/Ra-228 disequilibria in the otoliths of the much shorter-lived silver hake and flying fish may provide estimates of longevity on time scales of 0-10 years, which could then be used to evaluate the accuracy of currently-used ageing models based on otolith annulus counts. Age determinations of fish based on natural radioisotopes can result in significant improvements in the assessment and management of certain fisheries resources. (author)

  2. Horizontal distribution of natural radionuclides (Pb-210, Po-210, Ra-226, Th-232, K-40) and of toxic heavy metals (Pb, Co, Ni) in soil samples in the surroundings of a coal-fired power plant

    Bunzl, K.; Hoetzl, H.; Rosner, G.; Schmidt, W.; Winkler, R.

    1984-01-01

    The spatial distribution of the specific activities of the above radionuclides in the soil within 5 km of the plant as well as the ratios Pb-210/Ra-226 and Po-210/Ra-226 did not reveal any noticeable effects on the natural concentrations of these radionuclides in the soils. The specific activities of the radionuclides in the fly ash of the plant are obviously too small to disturb the natural distribution pattern significantly. A similar behaviour was observed for the concentrations of the heavy metals in the soils around the plant, which were also within the same range of values as observed for largely unpolluted soils. Increased metal concentrations in the soils downwind of the stack of the power plant were not observable. The concentrations of these metals in the fly ash were not sufficiently high to significantly change the local distribution of the elements in the soils in the surroundings of the plant. (orig./HP) [de

  3. Development of sequential analytical method for the determination of U-238, U-234, Th-232, Th-230, Th-228, Ra-226 and Ra-228 and its application in mineral waters

    Costa Lauria, D. da.

    1986-01-01

    A sequential analytical method for the determination of U-238, U-234, Th-232, Th-230, Th-228, Ra-226 and Ra-228 in environmental samples and applied to the analysis of mineral waters is studied. Thorium isotopes are coprecipitated with lanthanium fluoride before counting in alpha spectrometer, the uranium isotopes are determined by alpha spectrometry following extraction with TOPO onto a polymenic membrane. Radium-226 is determined with the radom emanation technique. (M.J.C.) [pt

  4. No adaptive response is induced by chronic low-dose radiation from Ra-226 in the CHSE/F fish embryonic cell line and the HaCaT human epithelial cell line

    Shi, Xiaopei, E-mail: shix22@mcmaster.ca; Mothersill, Carmel; Seymour, Colin

    2016-11-15

    Purpose: To determine whether chronic low-dose α-particle radiation from Ra-226 over multiple cell generations can lead to an adaptive response in CHSE/F fish embryonic cells or HaCaT human epithelial cells receiving subsequent acute high-dose γ-ray radiation. Methods: CHSE/F and HaCaT cells were exposed to very low doses of Ra-226 in medium for multiple generations prior to being challenged by a higher dose γ-ray radiation. The clonogenic assay was used to test the clonogenic survival of cells with or without being pretreated by radiation from Ra-226. Results: In general, pretreatment with chronic radiation has no significant influence on the reaction of cells to the subsequent challenge radiation. Compared to unprimed cells, the change in clonogenic survival of primed cells after receiving challenge radiation is mainly due to the influence of the chronic exposure, and there's little adaptive response induced. However at several dose points, pretreatment of CHSE/F fish cells with chronic radiation resulted in a radiosensitive response to a challenge dose of γ-ray radiation, and pretreatment of HaCaT cells resulted in no effect except for a slightly radioresistant response to the challenge radiation which was not significant. Conclusion: The results suggest that chronic low-dose radiation is not effective enough to induce adaptive response. There was a difference between human and fish cells and it may be important to consider results from multiple species before making conclusions about effects of chronic or low doses of radiation in the environment. The term “radiosensitive” or “adaptive” make no judgment about whether such responses are ultimately beneficial or harmful. - Highlights: • No obvious adaptive response is induced by chronic low-dose radiation from Ra-226. • Priming radiation from Ra-226 sensitized CHSE/F cells to the challenge radiation. • Linear model is inconsistent with current work using chronic low-dose radiation.

  5. Determination of radioactivity levels in phosphate-containing fertilizers, copper and gold ores by direct gamma-ray spectroscopy. U-238, Th-232, K-40, and Ra-226 in fertilizers and ores

    Constantinescu, B.; Constantin, F.; Dusoiu, N.; Pascovoici, G.

    1996-01-01

    Two particular sources from the natural radiation background which may be encountered in Romanian industry are here presented: the phosphate containing fertilizers and the gold and copper ores, respectively. U-238, Th-232, K-40, and Ra-226 activity levels for several imported phosphorites, superphosphates and also for concentrated Cu and Au indigenous ores are reported. A simple and efficient radioactivity determination procedure based on a large volume NaI(Tl) detector, coupled to a Romanian design portable multichannel analyzer is described. Potential radiological impacts for the specialized workers are also discussed. (author) 1 fig., 4 tabs. 6 refs

  6. Treatment of liquid wastes from uranium hydrometallurgy

    Moraga G, J.C.

    1988-01-01

    Different treatments for low activity liquid wastes, generated by the hidromettalurgy of uranium ore are studied. A process of treatment was chosen which includes a neutralization with lime and limestone and a selective removal of Ra-226, through ion-exchange resins. A plant, with a capacity of treatment of 1 m 3 /h of liquid effluents was scoped. (author)

  7. Treatment and conditioning of historical radioactive waste

    Dogaru, Ghe.; Dragolici, F.; Ionascu, L.; Rotarescu, Ghe.

    2009-01-01

    The paper describes the management of historical radioactive waste from the storage facility of Radioactive Waste Treatment Plant. The historical waste stored into storage facility of IFIN-HH consists of spent sealed radioactive sources, empty contaminated containers, wooden radioactive waste, low specific activity radioactive waste, contaminated waste as well as radioactive waste from operation of WWR-S research reactor. After decommissioning of temporary storage facility about 5000 packages with radioactive waste were produced and transferred to the disposal facility. A large amount of packages have been transferred and disposed of to repository but at the end of 2000 there were still about 800 packages containing cement conditioned radioactive waste in an advanced state of degradation declared by authorities as 'historical waste'. During the management of historical waste campaign there were identified: radium spent radioactive sources, containers containing other spent sealed radioactive sources, packages containing low specific activity waste consist of thorium scrap allow, 30 larger packages (316 L), packages with activity lower than activity limit for disposal, packages with activity higher than activity limit for disposal. At the end of 2008, the whole amount of historical waste which met the waste acceptance criteria has been conditioned and transferred to disposal facility. (authors)

  8. A method for conditioning radioactive-wastes

    Cuaz, Daniel; Thiery, Daniel.

    1974-01-01

    Description is given of a method for conditioning radioactive-wastes, according to the main patent. This method is characterized in that the radioactive wastes are constituted by radio-elements incorporated with filtration and/or floculation promoters. This can be applied to radioactive effluent processing [fr

  9. The conditioning of radioactive waste by bitumen

    Rodier, J.; Scheidhauer, J.; Malabre, M.

    1961-01-01

    The separation of radioactive sludge and waste by bitumen is studied. Results are given concerning various trials carried out on the lixiviation of the final product by water as a function of the pH, of the time, and of the composition. The conditions for carrying out this process of coating the waste are controlled from a radioactive point of view. (author) [fr

  10. Non-fuel cycle radioactive waste policy in Turkey

    Demirel, H.

    2003-01-01

    Radioactive wastes generated in Turkey are mostly low level radioactive waste generated from the operation of one research reactor, research centers and universities, hospitals, and from radiological application of various industries. Disused sealed sources which potentially represent medium and high radiological risks in Turkey are mainly Am-241, Ra-226, Kr-85, Co-60, Ir-192 and Cs-137. All radioactive waste produced in Turkey is collected, segregated, conditioned and stored at CWPSF. Main components of the facility are listed below: Liquid waste is treated in chemical processing unit where precipitation is applied. Compactable solids are compressed in a compaction cell. Spent sources are embedded into cement mortar with their original shielding. If the source activities are in several millicuries, sometimes dismantling is applied and segregated sources are conditioned in shielded drums. Due to increasing number of radiation and nuclear related activities, the waste facility of CNAEM is now becoming insufficient to meet the storage demand of the country. TAEA is now in a position to establish a new radioactive waste management facility and studies are now being carried out on the selection of best place for the final storage of processed radioactive wastes. Research and development studies in TAEA should continue in radioactive waste management with the aim of improving data, models, and concepts related to long-term safety of disposal of long-lived waste

  11. Conditioning CANDU reactor wastes for disposal

    Beamer, N.V.; Bourns, W.T.; Buckley, L.P.; Speranzini, R.A.

    1981-12-01

    A Waste Treatment Centre (WTC) is being constructed at the Chalk River Nuclear Laboratories to develop and demonstrate processes for converting reactor wastes to a form suitable for disposal. The WTC contains a starved air incinerator for reducing the volume of combustible solid wastes, a reverse osmosis section for reducing the volume of liquid wastes and an immobilization section for incorporating the conditioned wastes in bitumen. The incinerator is commissioned on inactive waste: approximately 16.5 Mg of waste packaged in polyethylene bags has been incinerated in 17 burns. Average weight and volume reductions of 8.4:1 and 32:1, respectively, have been achieved. Construction of the reverse osmosis section of WTC is complete and inactive commissioning will begin in 1982 January. The reverse osmosis section was designed to process 30,000 m 3 /a of dilute radioactive waste. The incinerator ash and concentrated aqueous waste will be immobiblized in bitumen using a horizontal mixer and wiped-film evaporator. Results obtained during inactive commissioning of the incinerator are described along with recent results of laboratory programs directed at demonstrating the reverse osmosis and bituminization processes

  12. Treatment and conditioning of radioactive solid wastes

    1992-07-01

    Radioactive materials are extensively used in industrial and research activities mainly related to medical, agricultural, environmental and other studies and applications. During the application and production of radioisotopes, significant amounts of radioactive wastes will inevitably arise, which must be managed (i.e. handled, treated, conditioned, intermediately stored and finally disposed of) with particular care. Serious efforts to minimize and appropriately segregate the waste arisings during the application of radioisotopes are the most important first step in waste management. The essential objective of the management of radioactive waste is the protection of mankind, the biosphere and the environment from the detrimental effects of nuclear radiation both now and in the future. This report deals with radioactive wastes outside the nuclear fuel cycle and it is directed primarily to countries without nuclear power programmes, e.g. countries belonging to the Groups A, B and C. Group A includes Member States which utilize radioisotopes at a few hospital locations, universities and industries. Group B includes Member States which have multi-use of radioisotopes in hospitals and other institutional areas and need a central collection and processing system. Group C includes Member States which have multi-use of radioisotopes and a nuclear research centre which is capable of indigenous production of several radioisotopes. When developing a waste management strategy, consideration should be given to the entire sequence of waste management operations from waste sources to disposal and all the related issues: every aspect of waste generation, processing, transportation, storage and disposal, including regulatory, socio-political and economic issues. The interaction of all these aspects must be analysed and understood before the entire waste management system can be properly built up and safely managed. 16 refs, 13 figs, 5 tabs

  13. Management of wastes from uranium mines and mills

    Thomas, K.T.

    1981-01-01

    Uranium mining and milling operations have not given rise to much concern about their hazards, and with advancing technologies for mill processing and waste management, the situation will continue to improve. However, the disposal of large quantities of waste produced in mining and milling does have an environmental impact, owing to the long half-lives and the ready availability of the toxic radionuclides Ra-226 and Rn-222. This article deals with the management of wastes from uranium mines and mills

  14. Conditioning of tritiated wastes. Part II

    Hawthorne, S.H.

    1984-01-01

    Work is continuing on the development of conditioning systems for low and intermediate level tritiated liquid and solid wastes which will prevent loss of tritium for at least 150 years. This portion of the program has concentrated on solidification and encapsulation of tritiated aqueous wastes, development of techniques, for the measurement of tritium loss in air and water, and identification and evaluation of encapsulation materials. Solidification of tritiated aqueous wastes by water extendible polyester or cements resulted in average tritium releases of approximately 1-4x10 -1 α/day with that from water extendible polyester being the lowest. The daily release rate is independent of initial tritium concentration in the waste form and can be reduced by a factor of 1000 by encapsultation of the waste within a 10 mm layer of water extendible polyester. Water extendible polyester is the preferred material for solidification and encapsulation of aqueous tritiated wastes and encapsulation of tritiated solids permitting release of only 3x10 -3 % of the original activity over 150 years. It is expected that this program which was originally scheduled for three years can now be completed in two years with complete definition of the conditioning system including the outer package

  15. Occupational monitoring in intracavitary radium therapy. Monitoracao de pessoas ocupacionalmente expostas no tratamento de cancer de colo uterino com Ra-226

    Araujo, A M.C. de [Instituto de Radioprotecao e Dosimetria (IRD), Rio de Janeiro, RJ (Brazil)

    1985-07-01

    In Brazil, the highest incidence of cancer in females is in the uterine cervix, in which Bracytherapy treatment plays a very important role. The majority of our Clinics use {sup 226}Ra or {sup 137}Cs tubes to perform this therapy. As many of these Clinics do not use the afterloading technique, we investigated the occupational exposure for the staffs belonging to two big Hospitals in Rio de Janeiro, where the working conditions are very different. Besides the normal film badge, placed in the upper part of the trunk, each person has been provided with seven additional thermoluminescent dosimeters (chips - {sup 7}LiF) placed at: left ring finger, right ring finger, forehead (between the eyes), over the thyroid, in the midle of the back and the front of the trunk, and over the gonadal region. In Hospital A, where the staff is composed of 1 medical doctor and 1 nurse, they treat about 13 patients per month. In Hospital B, the staff was composed of 12 medical doctors, 2 technicians and 7 murses, and about 20 patients are treated monthly. The occupational exposures have been investigated separately for each step of the {sup 226}Ra routine. From these results we could easily identify that: the nurses working in the infermary do not use the lateral lead protection of beds to clean the patients; in Hospital B, where there are perfect conditions for storage and manipulation of the radioactive sources, the technician in charge of these tasks, together with the transport of the applicator, except in his hands, suffers no exposure at all. Besides that, we could also see that in Hospital A, where the nurse plays also the role of that technician, and the local protection conditions are not correct, the estimated annual exposures are still below the annual limits according to ICRP N{sup 0}. 26/1977. This analysis has been completed with measures of occupational exposures in Clinics using the after loading technique. (author).

  16. Waste conditioning technology of radiocontaminated soil

    Chen Dahua; Wang Xiaoli; Chen Xin

    2012-01-01

    A special conditioning way for low level soil contaminated by 241 Am was discussed. Firstly, the contaminated soil was condensed in package container (200 L drum) by 20 t pressing machine. The contaminated soil was pressed from loose state to compaction state, and the volume reduction rate was from 1.1 to 1.4. Secondly, cement with thickness of 10 cm to 15 cm was poured on the package container for sealing. Thus, a cement sealing member was made up by contaminated soil and it could be described as normal solid waste. Finally, taking the cement sealing member as conditioning object, using Ⅶ steel trunk as package container and cement conditioning, Ⅶ steel trunk package was got. Through radiation monitoring, the Ⅶ steel trunk package can satisfy the transport requirement of radiation waste. Also, it can satisfy the accept and disposal requirements of national repository. (authors)

  17. Leaching methods for conditioned radioactive waste

    Carpentiero, R.; Bienvenu, P.; Huebra, A. G. de la; Dale, C.; Grec, D.; Gallego, C.; Rodriguez, M.; Vanderlinden, F.; Voors, P. I.; Welbergen, J.; May, R.; Fays, J.

    2005-01-01

    The physico-chemical characterization of solidified, real or simulated, radioactive waste is essential in determining their long-term stability in conditions close to that which could be encountered during disposal. The evaluation or prediction of the performance of conditioned waste passes through many suitable studies and experiments, according to a documented qualification programme. In this respect the leaching test is among the first important techniques to evaluate the feasibility of a waste form and for comparing and selecting the best waste form. So the leaching behaviour of an immobilized radioactive waste is a relevant property to be studied. The objective of the present report is to collect and describe the most representative leaching methods used in international laboratories, mainly at European level, whether standard or standard-derived. In this instance the work is a summary of the Network knowledge and applications on leaching processes in order to exchange information and scientific and technical experiences in this respect. The focus is to express all the relevant parameters of the test and its field of application. all this background is the needed starting point to clarify the similarities and shortcomings of the methods used in the EN-TRAP laboratories and, subsequently, the possible equalities or differences which can be attributed to the characteristic parameters of the different type of wastes treated. In order to comprise the significance and the effects of the parameters involved in leaching phenomena, an initial discussion on leaching mechanisms and on achievable results is made in this document. The international standardised methods are summarised as being the origin for all the network leaching procedures. This work in a preliminary way represents a comparative review ordered to introduce an unique leaching procedure to be tested in an interlaboratory comparative exercise. Further the unique method would be a quick internal reference

  18. Hydrothermal conditions around a radioactive waste repository

    Thunvik, R.; Braester, C.

    1981-12-01

    Numerical solutions for the hydrothermal conditions around a hard rock repository for nuclear fuel waste are presented. The objective of the present investigation is to illustrate in principle the effect of heat released from a hypothetical radioactive waste repository with regard to anisotropy in the rock permeability. Permeability and porosity are assumed to be constant or to decrease exponentially with depth. The hypothetical repository is situated below a horizontal ground surface or below the crest of a hill, and it is assumed that the water table follows the topography. Major interest in the analysis is directed towards the influence of anisotropy in the permeability on the flow patterns and travel times for water particles, being traced from the repository to the ground surface. The presented results show that anisotropy in the permeability may have a significant influence on the flow conditions around the repository and subsequently also on the travel times from the repository. (Authors)

  19. Reduction of radioactive waste by improvement of conditioning facilities

    Radde, E.

    2014-07-01

    The NES (Nuclear Engineering Seibersdorf) is the only radioactive waste conditions and storage facility in Austria. It manages waste originating from research, industry and medicine. Its main goal is, not only to treat and store waste safety, but also to optimize processes to further reduce the waste volume. To achieve this goal, the New Handling Facility was built. In this paper we will show how the waste volume can be easily reduced by optimizing the conditioning and waste stream process. The NES owns a water treatment plant for cleaning of active waste water, an incineration plant that is used to burn radioactive waste. (Author)

  20. Relations of equivalence of conditioned radioactive waste

    Kumer, L.; Szeless, A.; Oszuszky, F.

    1982-01-01

    A compensation for the wastes remaining with the operator of a waste management center, to be given by the agent having caused the waste, may be assured by effecting a financial valuation (equivalence) of wastes. Technically and logically, this equivalence between wastes (or specifically between different waste categories) and financial valuation has been established as reasonable. In this paper, the possibility of establishing such equivalences are developed, and their suitability for waste management concepts is quantitatively expressed

  1. CONDITIONING OF INTERMEDIATE-LEVEL WASTE AT FORSCHUNGSZENTRUM JUELICH GMBH

    Krumbach, H.

    2003-01-01

    This contribution to the group of low-level, intermediate, mixed and hazardous waste describes the conditioning of intermediate-level mixed waste (dose rate above 10 mSv/h at the surface) from Research Centre Juelich (FZJ). Conditioning of the waste by supercompaction is performed at Research Centre Karlsruhe (FZK). The waste described is radioactive waste arising from research at Juelich. This waste includes specimens and objects from irradiation experiments in the research reactors Merlin (FRJ-1) and Dido (FRJ-2) at FZJ. In principle, radioactive waste at Forschungszentrum Juelich GmbH is differentiated by the surface dose rate at the waste package. Up to a surface dose rate of 10 mSv/h, the waste is regarded as low-level. The radioactive waste described here has a surface dose rate above 10 mSv/h. Waste up to 10 mSv/h is conditioned at the Juelich site according to different conditioning methods. The intermediate-level waste can only be conditioned by supercompaction in the processing facility for intermediate-level waste from plant operation at Research Centre Karlsruhe. Research Centre Juelich also uses this waste cell to condition its intermediate-level waste from plant operation

  2. Different Methods for Conditioning Chloride Salt Wastes

    De Angelis, G.; Fedeli, C.; Capone, M.; Marzo, G.A.; Mariani, M.; Da Ros, M.; Giacobbo, F.; Macerata, E.; Giola, M.

    2015-01-01

    Three different methods have been used to condition chloride salt wastes coming from pyro-processes. Two of them allow to synthesise sodalite, a naturally occurring mineral containing chlorine: the former, starting from Zeolite 4A, which transforms the zeolite into sodalite; the latter, which starts from kaolinite, giving sodalite as well. In addition, a new matrix, termed SAP (SiO 2 -Al 2 O 3 -P 2 O 5 ), has been synthesised. It is able to form different mineral phases which occlude fission metals. The products from the different processes have been fully characterised. In particular the chemical durability of the final waste forms has been determined using the standard product consistency test. According to the results obtained, SAP seems to be a promising matrix for the incorporation of chloride salt wastes from pyro-processes. Financial support from the Nuclear Fission Safety Programme of the European Union (projects ACSEPT, contract FP7-CP-2007- 211 267, and SACSESS, Collaborative Project 323282), as well as from Italian Ministry for Economic Development (Accordo di Programma: Piano Annuale di Realizzazione 2008-2009) is gratefully acknowledged. (authors)

  3. Conditioning characterization of low level radioactive waste

    Osman, A. F.

    2010-12-01

    This study has been carried out in the radioactive waste management laboratory Sudan Atomic Energy Commission. The main purpose of this work is method development for treatment and conditioning of low level liquid waste in order to improve radiation protection level in the country. For that purpose a liquid radioactive material containing Cs-137 was treated using the developed method. In the method different type of materials (cement, sands, concrete..etc) were tested for absorption of radiation emitted from the source as well as suitability of the material for storage for long time. It was found that the best material to be used is Smsmia concrete. Where the surface dose reduced from 150 to 3μ/h. Also design of storage container was proposed (with specification: diameter 6.5 cm, height 6 cm, placed in internal cylinder of diameter 10.3 cm, height 12.3 cm) and all are installed on the concrete and cement in the cylinder. Method was used in the process of double-packaging configuration. For more protection it is proposed that a mixed of cement to fill the void in addition to the sand be added to ensure low amount of radiation exposure while transport or storage. (Author)

  4. Study on technology for radioactive waste treatment and management from uranium production

    Vu Hung Trieu; Vu Thanh Quang; Nguyen Duc Thanh; Trinh Giang Huong; Tran Van Hoa; Hoang Minh Chau; Ngo Van Tuyen; Nguyen Hoang Lan; Vuong Huu Anh

    2007-01-01

    There is some solid and liquid radioactive waste created during producing Uranium that needs being treated and managed to keep our environment safe. This radioactive waste contains Uranium (U-238), Thorium (Th-232), Radium (Ra-226) and some heavy metals and mainly is low radioactive waste. Our project has researched and built up appropriate technology for treating and managing the radioactive waste. After researching and experimenting, we have built up four technology processes as follows: Technology for separating Radium from liquid waste; Technology for treating and managing solid waste containing Ra; Technology for separating Thorium from liquid waste after recovering radium; Technology for stabilizing solid waste from Uranium production. (author)

  5. Radioactivity in wastes generated from shale gas exploration and production - North-Eastern Poland.

    Jodłowski, Paweł; Macuda, Jan; Nowak, Jakub; Nguyen Dinh, Chau

    2017-09-01

    In the present study, the K-40, U-238, Ra-226, Pb-210, Ra-228 and Th-228 activity concentrations were measured in 64 samples of wastes generated from shale gas exploration in North-Eastern Poland. The measured samples consist of drill cuttings, solid phase of waste drilling muds, fracking fluids, return fracking fluids and waste proppants. The measured activity concentrations in solid samples vary in a wide range from 116 to around 1100 Bq/kg for K-40, from 14 to 393 Bq/kg for U-238, from 15 to 415 Bq/kg for Ra-226, from 12 to 391 Bq/kg for Pb-210, from a few Bq/kg to 516 Bq/kg for Ra-228 and from a few Bq/kg to 515 Bq/kg for Th-228. Excluding the waste proppants, the measured activity concentrations in solid samples oscillate around their worldwide average values in soil. In the case of the waste proppants, the activity concentrations of radionuclides from uranium and thorium decay series are significantly elevated and equal to several hundreds of Bq/kg but it is connected with the mineralogical composition of proppants. The significant enhancement of Ra-226 and Ra-228 activity concentrations after fracking process was observed in the case of return fracking fluids, but the radium isotopes content in these fluids is comparable with that in waste waters from copper and coal mines in Poland. Copyright © 2017 Elsevier Ltd. All rights reserved.

  6. Conditioning of radioactive waste solutions by cementation

    Vejmelka, P.; Rudolph, G.; Kluger, W.; Koester, R.

    1992-02-01

    For the cementation of the low and intermediate level evaporator concentrates resulting from the reprocessing of spent fuel numerous experiments were performed to optimize the waste form composition and to characterize the final waste form. Concerning the cementation process, properties of the waste/cement suspension were investigated. These investigations include the dependence of viscosity, bleeding, setting time and hydration heat from the waste cement slurry composition. For the characterization of the waste forms, the mechanical, thermal and chemical stability were determined. For special cases detailed investigations were performed to determine the activity release from waste packages under defined mechanical and thermal stresses. The investigations of the interaction of the waste forms with aqueous solutions include the determination of the Cs/Sr release, the corrosion resistance and the release of actinides. The Cs/Sr release was determined in dependence of the cement type, additives, setting time and sample size. (orig./DG) [de

  7. DEPENDENCE OF WASTE PAPER QUALITATIVE INDICES ON ITS STORAGE CONDITIONS

    I. Karpunin

    2012-01-01

    Full Text Available The paper investigates an influence of component quantity (lignin, cellulose and hemicellulose on qualitative (physical and mechanical indices of waste-paper in relation to its storage period and weather conditions. It has been established that while storing (in waste dumps waste paper it is to be kept at a definite temperature and humidity in order to reduce impact of weather conditions.

  8. THE CONDITION OF WASTE MANAGEMENT IN ROMANIA

    Diana ZAGAN ZELTER

    2009-01-01

    Full Text Available The present article approaches a very important and actual theme andthat is the problem of generating waste in Romania which, on one hand,affects the environment and human health, and on the other hand itreflects the inefficient way of using the natural resources in society.Probably the majority of us have thought or hoped that the naturalresources are inexhaustible, but we can see today that the unwiseexploitation of these resources is threatening our future.Waste management is a difficult and complex problem in Romania whichis far from being solved according to the environment rules of theEuropean Union. The worsening of the waste problem, especially of thedomestic waste is generated by the significant increase of its quantity, aswell as by the inappropriate way of solving different stages of wasteprocessing.

  9. Handling and storage of conditioned high-level wastes

    1983-01-01

    This report deals with certain aspects of the management of one of the most important wastes, i.e. the handling and storage of conditioned (immobilized and packaged) high-level waste from the reprocessing of spent nuclear fuel and, although much of the material presented here is based on information concerning high-level waste from reprocessing LWR fuel, the principles, as well as many of the details involved, are applicable to all fuel types. The report provides illustrative background material on the arising and characteristics of high-level wastes and, qualitatively, their requirements for conditioning. The report introduces the principles important in conditioned high-level waste storage and describes the types of equipment and facilities, used or studied, for handling and storage of such waste. Finally, it discusses the safety and economic aspects that are considered in the design and operation of handling and storage facilities

  10. Overview of treatment and conditioning of low-level wastes

    Trevorrow, L.

    1986-01-01

    The consideration of alternative technologies in low-level waste management is assumed to be partly a response to current demands for lower risk in waste disposal. One of the determinants of risk in waste disposal is the set of characteristics of the materials placed into disposal cells, i.e., the products of treatment and conditioning operations. The treatment and conditioning operations that have been applied to waste streams are briefly examined. Three operations are the most important determinants of the stability that will contribute to reducing risk at the disposal cell: compaction, high-integrity containers, and solidification. The status of these three operations is reviewed

  11. Conditioning of uranium-containing technological radioactive waste

    Smodis, B.; Tavcar, G.; Stepisnik, M.; Pucelj, B.

    2006-01-01

    Conditioning of mostly liquid uranium containing technological radioactive waste emerging from the past research activities at the Jozef Stefan Institute is described. The waste was first thoroughly characterised, then the radionuclides present solidified by appropriate chemical treatment, and the final product separated and prepared for storage in compliance with the legislation. The activities were carried out within the recently renewed Hot Cells Facility of the Jozef Stefan Institute and the overall process resulted in substantial volume reduction of the waste initially present. (author)

  12. Conditioning of low- and intermediate-level radioactive wastes

    1983-01-01

    The nuclear fuel cycle, together with the use of separated radioisotopes, in many endeavours generates a variety of low- and intermediate-level radioactive wastes. These waste materials contain quantities of radionuclides sufficient to present potential health risks to people if the wastes are not adequately managed, but usually insufficient quantities to require heat removal. Adequate management involves a series of steps which lead from the arising of the wastes to their safe disposal, steps which may include collection, segregation, treatment, volume reduction, conditioning, transport, interim storage and disposal. Each step is defined by the need to accommodate to the preceding one and to facilitate the ones that follow. This technical report describes primarily the technologies available for the conditioning steps (i.e., immobilization and packaging) and relates them to the other steps. In broad terms, the purpose of conditioning is to convert the wastes into packages that are suitable for transport, storage and disposal

  13. Handling and storage of conditioned high-level wastes

    Heafield, W.

    1984-01-01

    This paper deals with certain aspects of the management of one of the most important radioactive wastes arising from the nuclear fuel cycle, i.e. the handling and storage of conditioned high-level wastes. The paper is based on an IAEA report of the same title published during 1983 in the Technical Reports Series. The paper provides illustrative background material on the characteristics of high-level wastes and, qualitatively, their requirements for conditioning. The principles important in the storage of high-level wastes are reviewed in conjunction with the radiological and socio-political considerations involved. Four fundamentally different storage concepts are described with reference to published information and the safety aspects of particular storage concepts are discussed. Finally, overall conclusions are presented which confirm the availability of technology for constructing and operating conditioned high-level waste storage facilities for periods of at least several decades. (author)

  14. Safe disposal of nuclear waste in rock formations - Geological conditions - What level of safety do we require and what can we attain

    Devell, L.

    1977-01-01

    Proceeding from the imprecise expressions 'completely safe', 'highest conceivable safety level' and 'highest possible safety level', the level of safety of the final disposal of radioactive wastes is discussed. The Scandinavian radiation protection authorities have established guidelines for the long-term collective radiation doses per MW(e)year, and already guidelines are becoming clear covering the whole nuclear power era. Aspects of risk analysis and cost-benefit analysis are also discussed. The concepts 'site multiplicity' and 'technical irreversibility' are introduced. Assuming that wastes are contained in glass, or in spent fuel rods, the potential risk indices as a function of time are presented. In the first 300 years Cs137 and Sr90 dominate. Threeafter Am241 until 3000 years, when Am243 and Pu239 take over. In the long term Ra226 becomes significant also. After 1000 years however, the potential risk is no greater than that of uranium ore, when accessibility becomes the dominant consideration. Factors which could lead to dispersal of the wastes are listed, and finally a rough calculation of the activity reaching a well from leaching of activities from glass in a ground water flow is presented. (JIW)

  15. The conditioning of low-level waste and of hazardous waste in Austria

    Krejsa, P.

    1988-01-01

    In 1978 in Austria some 50% (total 30%) of the people voted against the use of nuclear power for the production of electricity. Nevertheless radioactive wastes are produced in Austria from hospitals, industrial and research activities. The concept of waste management was therefore not altered. This paper discusses how, due to the low amounts of wastes (some 200 m 3 /y), of high costs of the waste treatment and of the concept of a central final disposal for radwastes the research center Seibersdorf was charged with the task to act as central storage and conditioning plant for the wastes arising from Austria

  16. Inspection and testing in conditioning of radioactive waste

    1997-08-01

    This report was prepared as part of the IAEA's programme on quality assurance and quality control requirements for radioactive waste packages. The report provides guidance and rationale for the application of inspections and tests as part of the entire quality assurance programme to verify and demonstrate that waste conditioning is being performed in a manner that protects human health and the environment from hazards associated with radioactive waste. The report is relevant to the Technical Reports Series No. 376, ''Quality Assurance for Radioactive Waste Packages'' dealing in general with the quality assurance programme of organization consigning radioactive waste to the repository, and elaborates its section devoted to inspection and testing for acceptance. 14 refs, 7 figs

  17. Radon emission from uranium mining waste rock dumps and resulting radon immission; Radonemissionsverhalten von Halden des Uranbergbaus und daraus resultierende Radonemissionen

    Regner, J.; Hinz, W.; Schmidt, P. [Wismut GmbH, Chemnitz (Germany)

    2016-07-01

    Since more than 20 years, Wismut GmbH has been investigating the radon situation at uranium mining waste rock dumps. In the present paper the results of 19 complex studies at uranium mining dumps in the Erzgebirge (Ore Mountains) are reported. Although the mean specific activity of Ra-226 of the waste rock material was on a rather low level of about 0.5 Bq/g, the mean radon concentration in free atmosphere at the public exposure sites in the immediate vicinity of the dumps reached a value of about 1000 Bq/m{sup 3} for a half-year exposition and of about 600 Bq/m{sup 3} for a one-year exposition. Certain geometries and structures of waste rock dumps and the occurrence of convective airflows in the dumps are main reasons for the high radon emission despite of the relatively low specific Ra-226 activity. A case study for two buildings directly on the top of a waste rock dump in the town Johanngeorgenstadt is presented. The hypothetical interpolation of the results for Ra-226-activity to a value below the threshold value of 0.2 Bq/g leads to the assumption that problematic radon situations may also occur outside the areas of legacies of uranium mining. Considering the aspects mentioned, a clearance level for NORM of 1 Bq/g is questionable.

  18. Evaluation of conditioned high-level waste forms

    Mendel, J.E.; Turcotte, R.P.; Chikalla, T.D.; Hench, L.L.

    1983-01-01

    The evaluation of conditioned high-level waste forms requires an understanding of radiation and thermal effects, mechanical properties, volatility, and chemical durability. As a result of nuclear waste research and development programs in many countries, a good understanding of these factors is available for borosilicate glass containing high-level waste. The IAEA through its coordinated research program has contributed to this understanding. Methods used in the evaluation of conditioned high-level waste forms are reviewed. In the US, this evaluation has been facilitated by the definition of standard test methods by the Materials Characterization Center (MCC), which was established by the Department of Energy (DOE) in 1979. The DOE has also established a 20-member Materials Review Board to peer-review the activities of the MCC. In addition to comparing waste forms, testing must be done to evaluate the behavior of waste forms in geologic repositories. Such testing is complex; accelerated tests are required to predict expected behavior for thousands of years. The tests must be multicomponent tests to ensure that all potential interactions between waste form, canister/overpack and corrosion products, backfill, intruding ground water and the repository rock, are accounted for. An overview of the status of such multicomponent testing is presented

  19. NNWSI waste form test method for unsaturated disposal conditions

    Bates, J.K.; Gerding, T.J.

    1985-03-01

    A test method has been developed to measure the release of radionuclides from the waste package under simulated NNWSI repository conditions, and to provide information concerning materials interactions that may occur in the repository. Data are presented from Unsaturated testing of simulated Savannah River Laboratory 165 glass completed through 26 weeks. The relationship between these results and those from parametric and analog testing are described. The data indicate that the waste form test is capable of producing consistent, reproducible results that will be useful in evaluating the role of the waste package in the long-term performance of the repository. 6 refs., 7 figs., 5 tabs

  20. Studies of reactor waste conditioning and disposal at CRNL

    Beamer, N.V.; Bourne, W.T.; Buckely, L.P.; Pettipas, W.H.; Burrill, K.A.; Dixon, D.F.; Charlesworth, D.H.

    1982-09-01

    This report is a compilation of five papers presented at the Second Annual Meeting of the Canadian Nuclear Society in Ottawa, 1981 June. These papers describe recent progress in studies being conducted at the Chalk River Nuclear Laboratories related to the permanent disposal of low-and intermediate-level wastes arising in the Canadian nuclear industry. The principal topics discussed include waste processing by incineration, ultrafiltration and reverse osmosis, immobilization in bitumen and glass, and also the strategy for disposal of the conditioned wastes

  1. Treatment and final conditioning of solid radioactive wastes

    Cerre, J.

    1960-01-01

    The storage of solid radioactive wastes on a site is so cumbersome and dangerous that we have developed a method of treatment and conditioning by means of which the volume of waste is considerably reduced and very long-lasting shielding can be provided. This paper describes the techniques adopted at Saclay, where the wastes are sheared, compressed and enveloped in concrete of variable thickness. The main part of the report is devoted to a description of the corresponding remote handling installation. (author) [fr

  2. Fuel corrosion processes under waste disposal conditions

    Shoesmith, D.W.

    2000-01-01

    The release of the majority of radionuclides from spent nuclear fuel under permanent disposal conditions will be controlled by the rate of dissolution of the UO 2 fuel matrix. In this manuscript the mechanism of the coupled anodic (fuel dissolution) and cathodic (oxidant reduction) reactions which constitute the overall fuel corrosion process is reviewed, and the many published observations on fuel corrosion under disposal conditions discussed. The primary emphasis is on summarizing the overall mechanistic behaviour and establishing the primary factors likely to control fuel corrosion. Included are discussions on the influence of various oxidants including radiolytic ones, pH, temperature, groundwater composition, and the formation of corrosion product deposits. The relevance of the data recorded on unirradiated UO 2 to the interpretation of spent fuel behaviour is included. Based on the review, the data used to develop fuel corrosion models under the conditions anticipated in Yucca Mountain (NV, USA) are evaluated

  3. Conditioning radioactive wastes by means of thermosetting resins

    Auboing, G.; Limongi, A.; Thiery, D.

    1976-01-01

    The principle of the conditioning process of low and medium activity wastes by means of thermosetting resins is described. The two major phases of its application, viz: pre-treatment and coating are analysed. Finally as an example, the plant where this conditioning process is put into application (currently in operation at the Nuclear Study Center of Grenoble) is described [fr

  4. Radioactive sodium waste treatment and conditioning. Review of main aspects

    2007-01-01

    This publication reviews the main aspects relating to the treatment and conditioning of radioactive sodium waste. This waste arises from the operation of liquid metal fast reactors (LMFRs). In this type of reactor, sodium (Na) or sodium-potassium alloys (NaK) are used as a low-effect neutron moderating coolant medium for extracting and transferring thermal energy from the core and they represent a significant technical and safety challenge during operation and decommissioning. This publication provides the reader with technologically oriented information on the present status of sodium waste management approaches and recent achievements related to treatment and conditioning, with the objective of facilitating planning and preparatory work for the decommissioning of LMFRs. This publication provides a comprehensive review of the hazards associated with sodium waste management. Given the large quantities of sodium waste arising during decommissioning or reactor refurbishment, as well as the challenges and varied techniques associated with removal of 100% of all sodium and NaK bulk quantities and residues during decommissioning, a hazards review and analysis is a critical component in planning the dismantling and waste management activities. Roughly half of this publication focuses on sodium waste generating, handling and treatment processes. This includes draining sodium and NaK from plant systems; in situ treatment of residual sodium; cutting techniques for pumps, valves, piping and other components; cleaning of components; potential reuse of sodium; and removal of selected radionuclides from sodium waste with the objective of reducing the waste classification or converting it to exempt waste. The focus is on proven techniques and technologies, and each discussed method includes a review of the associated principle or theory, practical applications, advantages and disadvantages, limitations, industry experience, and final waste products. A review is provided of final

  5. Development of thermal conditioning technology for alpha-contaminated wastes

    Kim, Joon Hyung; Kim, H. Y.; Kim, J. G.

    2001-04-01

    To develop a thermal conditioning technology for alpha-contaminated wastes, which are presumed to generate from pyrochemical processing of spent fuel, research on the three different fields have been performed; incineration, off-gas treatment, and vitrification/cementation technology. Through the assessment on the amount of alpha-contaminated waste and incineration characterises, an oxygen-enriched incineration process, which can greatly reduce the off-gas volume, was developed by our own technology. Trial burn test with paper waste resulted in a reduction of off-gas volume by 3.5. A study on the behavior and adsorption of nuclides/heavy metals at high-temperature was performed to develop an efficient removal technology. Off-gas treatment technologies for radioiodine at high-temperature and 14 CO 2 , acidic gases, and radioactive gaseous wastes such as Xe/Kr at room temperature were established. As a part of development of high-level waste solidification technology, manufacture of high-frequency induction melter, fabrication and characterization of base-glass media fabricated with spent HEPA filter medium, and development of titanate ceramic material as a precursor of SYNROC by a self-combustion method were performed. To develop alpha-contaminated waste solidification technology, a process to convert periodontal in the cement matrix to calcite with SuperCritical Carbon Dioxide (SCCD) was manufactured. The SCCD treatment enhanced the physicochemical properties of cement matrices, which increase the long-term integrity of cement waste forms during transportation and storage

  6. Fuel corrosion processes under waste disposal conditions

    Shoesmith, D.W.

    1999-09-01

    Under the oxidizing conditions likely to be encountered in the Yucca Mountain Repository, fuel dissolution is a corrosion process involving the coupling of the anodic dissolution of the fuel with the cathodic reduction of oxidants available within the repository. The oxidants potentially available to drive fuel corrosion are environmental oxygen, supplied by the transport through the permeable rock of the mountain and molecular and radical species produced by the radiolysis of available aerated water. The mechanism of these coupled anodic and cathodic reactions is reviewed in detail. While gaps in understanding remain, many kinetic features of these reactions have been studied in considerable detail, and a reasonably justified mechanism for fuel corrosion is available. The corrosion rate is determined primarily by environmental factors rather than the properties of the fuel. Thus, with the exception of increase in rate due to an increase in surface area, pre-oxidation of the fuel has little effect on the corrosion rate

  7. Fuel corrosion processes under waste disposal conditions

    Shoesmith, D.W. [Univ. of Western Ontario, Dept. of Chemistry, London, Ontario (Canada)

    1999-09-01

    Under the oxidizing conditions likely to be encountered in the Yucca Mountain Repository, fuel dissolution is a corrosion process involving the coupling of the anodic dissolution of the fuel with the cathodic reduction of oxidants available within the repository. The oxidants potentially available to drive fuel corrosion are environmental oxygen, supplied by the transport through the permeable rock of the mountain and molecular and radical species produced by the radiolysis of available aerated water. The mechanism of these coupled anodic and cathodic reactions is reviewed in detail. While gaps in understanding remain, many kinetic features of these reactions have been studied in considerable detail, and a reasonably justified mechanism for fuel corrosion is available. The corrosion rate is determined primarily by environmental factors rather than the properties of the fuel. Thus, with the exception of increase in rate due to an increase in surface area, pre-oxidation of the fuel has little effect on the corrosion rate.

  8. Naturally occurring radioactive materials (NORM) wastes in oil fields are a radiological problem, but they are useful tools

    Othman, Ibrahim; Al-Masri, Mohammad Said

    2008-01-01

    Produced water, scales and sludges associated with the production of oil and gas contains enhanced concentrations of radium isotopes. Uncontrolled disposal of these wastes could lead to environmental pollution and thus to radiation exposure of members of the public. In the present work, radium isotopes in scales accumulated in oil field equipment, and produced water have been used for dating the deposited scales, studying between wells interactions and water flooding processes in addition to dating contaminated soils in the Syrian oil fields. The 228 Ra/ 226 Ra activity ratio in scales can be considered a fingerprint of the Th/U mass ratio in the geological formation of the reservoir. The 228 Ra/ 226 Ra activity ratio variations were found to reflect the variability of the Th/U mass ratio of the geological formation, suggesting two different source rock types found in the Syrian oil fields. The calculated mean Th/U mass ratio for these two possible types of source rock were 2.4 and 5.78. In addition, the 228 Ra/ 226 Ra mean activity ratio was also used to estimate the age of some deposited scales in tubulars; the results were compared with the 224 Ra/ 228 Ra activity ratio dating method. Moreover, 228 Ra/ 226 Ra, 224 Ra/ 228 Ra and 210 Pb/ 226 Ra activities ratios in contaminated soils due to disposal of production water were used to date contaminated sites at the oil fields; the results have been found to be in agreement with the actual disposal date. The methods can be used by the regulatory body to assess any uncontrolled disposal of such waste. (author)

  9. Sequential chemical treatment of radium species in TENORM waste sludge produced from oil and natural gas production

    El Afifi, E.M.; Awwad, N.S.; Hilal, M.A.

    2009-01-01

    This paper is dedicated to the treatment of sludge occurring in frame of the Egyptian produced from oil and gas production. The activity levels of three radium isotopes: Ra-226 (of U-series), Ra-228 and Ra-224 (of Th-series) in the solid TENORM waste (sludge) were first evaluated and followed by a sequential treatment for all radium species (fractions) presented in TENORM. The sequential treatment was carried out based on two approaches 'A' and 'B' using different chemical solutions. The results obtained indicate that the activity levels of all radium isotopes (Ra-226, Ra-228 and Ra-224) of the environmental interest in the TENORM waste sludge were elevated with regard to exemption levels established by IAEA [International Atomic Energy Agency (IAEA), International basic safety standards for the protection against ionizing radiation and for the safety of radiation sources. GOV/2715/Vienna, 1994]. Each approach of the sequential treatment was performed through four steps using different chemical solutions to reduce the activity concentration of radium in a large extent. Most of the leached radium was found as an oxidizable Ra species. The actual removal % leached using approach B was relatively efficient compared to A. It is observed that the actual removal percentages (%) of Ra-226, Ra-228 and Ra-224 using approach A are 78 ± 2.8, 64.8 ± 4.1 and 76.4 ± 5.2%, respectively. Whereas in approach A, the overall removal % of Ra-226, Ra-228 and Ra-228 was increased to ∼91 ± 3.5, 87 ± 4.1 and 90 ± 6.2%, respectively

  10. Characterization of conditioned low- and intermediate-level wastes

    Alexandre, D.; Pottier, P.; Billon, A.; Bourdrez, J.; Nomine, J.C.; Tassigny, C. de

    1983-01-01

    All radioactive wastes must be conditioned to satisfy the criteria for disposal of them in the ground. In accordance with the specifications laid down by the Agence nationale pour la gestion des dechets radioactifs (French National Agency for Radioactive Waste Management - ANDRA), waste characterization records must be drawn up, with the relevant tests being carried out under approved conditions. The paper summarizes the principal results acquired in laboratories of the French Atomic Energy Commission (CEA) under the characterization programme, which was initiated by ANDRA and to which the Commission of European Communities (CEC) has contributed within the framework of its five-year indirect-action programme (1980-84). The principal aspects of these characterization tests are concerned with leaching from normal-sized packages, techniques measuring the radioisotope diffusion rate in thermosetting resins, study of the chemical forms of the radioisotopes released and assessment of the resistance of the coatings to the action of micro-organisms in the soil. (author)

  11. Some aspects on the conditioning of the molecular sieves waste

    Deneanu, N.; Dulama, M.; Teoreanu, I.

    2009-01-01

    The paper deals with a systematic approach of some important problems, concerning the conditioning of the molecular sieves wastes resulted from Cernavoda Nuclear Power Plant using binder materials, ensuring the prerequisites for elaboration of the recipes of the waste forms. In order to justify the more or less different behavior of wide range of potential binder materials (high alumina cement, Type II Portland blast furnace cement, Type I normal Portland cement) in relation to the molecular sieves content, within the paper there were studied the leach rates of tritium and the compressive strengths. Moreover, the research work took into consideration the correlations between composition-processing-proprieties, mixing properties (workability) and hardening process (setting time). Typical properties and limits of the molecular sieves waste forms could meet the Waste Acceptance Criteria of the disposal site. The experimental results suggest that, the normal Portland cement is the best binder material for immobilizing molecular sieves wastes while addition of sand and dispersed agent into matrices would greatly enhance the properties of the waste forms. (authors)

  12. Conditions for precipitation of copper phases in DWPF waste glass

    Schumacher, R.F.; Ramsey, W.G.

    1993-01-01

    The Defense Waste Processing Facility (DWPF) precipitate hydrolysis process requires the use of copper formate catalyst. The expected absorbed radiation doses to the precipitate require levels of copper formate that increase the potential for the precipitation of metallic copper in the DWPF Melter. The conditions required to avoid the precipitation of copper are described

  13. 40 CFR 273.8 - Applicability-household and conditionally exempt small quantity generator waste.

    2010-07-01

    ... conditionally exempt small quantity generator waste. 273.8 Section 273.8 Protection of Environment ENVIRONMENTAL....8 Applicability—household and conditionally exempt small quantity generator waste. (a) Persons... universal wastes defined at § 273.9; and/or (2) Conditionally exempt small quantity generator wastes that...

  14. Women waste pickers: living conditions, work, and health.

    Coelho, Alexa Pupiara Flores; Beck, Carmem Lúcia Colomé; Fernandes, Marcelo Nunes da Silva; Freitas, Natiellen Quatrin; Prestes, Francine Cassol; Tonel, Juliana Zancan

    2016-09-29

    To know the elements of work, health, and living conditions of women who pick recyclable waste and are members of a waste cooperative in a town of the state of Rio Grande do Sul, Brazil. This is a qualitative, exploratory and descriptive study with seven subjects. Data were collected through participative observation, semi structured interview, and a focus group from July to August of 2013. The data were subjected to content analysis. The following thematic categories emerged: Women's work, informality and precariousness; Experiences of job satisfaction; and Working conditions and health: experiences with accidents, illness and health services. It was concluded that the women who collect recyclable material are exposed to precarious work conditions and potential health risks, such as work overload, accidents, illness, and social insecurity, and that nurses are responsible for promoting actions that ensure the health and inclusion of these workers.

  15. Innovative waste treatment and conditioning technologies at nuclear power plants

    2006-05-01

    The objective of this publication is to provide Member States with information on the most innovative technologies and strategies used in waste treatment and conditioning. At present, some of those technologies and strategies might not be widely implemented at nuclear power plants (NPP), but they have an important potential for their use as part of the long range NPP, utility, or national strategy. Thus, the target audience is those decision makers at the national and organizational level responsible for selecting waste processing technologies and strategies over a period of three to ten years. Countries and individual nuclear plants have limited financial resources which can be applied toward radioactive waste processing (treatment and conditioning). They are challenged to determine which of the many available technologies and strategies are best suited to meet national or local needs. This publication reduces the selection of processes for wastes generated by nuclear power plants to those technologies and strategies which are considered innovative. The report further identifies the key benefits which may derive from the adoption of those technologies, the different waste streams to which each technology is relevant, and the limitations of the technologies. The technologies and strategies identified have been evaluated to differentiate between (1) predominant technologies (those that are widely practiced in multiple countries or a large number of nuclear plants), and (2) innovative technologies (those which are not so widely used but are considered to offer benefits which make them suitable for broader application across the industry). Those which fall into the second category are the primary focus of this report. Many IAEA publications address the technical aspects of treatment and conditioning for radioactive wastes, covering research, technological advances, and safety issues. These studies and reports primarily target the research and technical staff of a

  16. Methods of conditioning waste fuel decladding hulls and dissolver residues

    De Regge, P.; Loida, A.; Schmidt-Hansberg, T.; Sombret, C.

    1985-01-01

    Several methods for conditioning spent fuel decladding hulls or dissolver residues have been considered in various countries of the European Community. Five of these methods used embedding technique with or without prior compaction: they are based on incorporation in metallic alloys, glass, ceramics, cements and metals or graphite compounds. A sixth one consists in melting the decladding materials. The corresponding research programmes have been pursued to varying states of progress with regard to demonstrating their feasibility on an industrial scale and the use of genuine wastes in bench scale experiments. The properties of the conditioned wastes have been investigated. Special attention has been paid to the corrosion resistance to various aqueous media as tap water, brine or clayey water. Although no categorical conclusion can be drawn from the initial results, the available findings provide a basis for assessing the different processes

  17. Decay calculations on medium-level and actinide-containing wastes from the LWR fuel cycle. Pt. 2

    Haug, H.O.

    1981-12-01

    1. The radiotoxicity index as inherent property of the radionuclide inventory was calculated for medium-level and actinide-containing wastes. The calculations were based on the annual limits of intake of the German Radiation Protection Ordinance as well as the new values of annual limits of intake from ICRP-30. The latter imply a higher rating of the toxicity of transuranium nuclides and a lower rating of Sr-90, Tc-99, and Ra-226. Thus, the annual radiotoxicity index is controlled by the transuranics after 10 to 100 years. 2. From the comparison of the radiotoxicity index of conditional and packed wastes with the same volume of uranium ore, it was evaluated that the relative radiotoxicity of the medium-level wastes decreases below the level of pitchblende after less than 100 years and below a 3% uranium ore after less than 2000 of decay. However, based on ICRP-30, the relative radiotoxicity index decreases below the level of pitchblende after 1000 years and decays to the level of the 3% uranium ore at about 10 5 years. 3. The comparison of the radiotoxicity concentration of the total disposal layer with a uranium ore deposit shows that the radiotoxicity concentration based on ICRP-30 of the self-heating wastes placed in single boreholes decays within 2000 years (high level waste within 3000 years) below the level of a uranium ore deposit of 0.2% uranium. The radiotoxicity concentration of the medium-level process waste and the alpha-waste disposed off in disposal chambers decreases to the level of a uranium ore deposit with 0.4 to 6% uranium after about 10 4 years, and 1% after about 10 5 years. (orig./HP) [de

  18. Treatment of waste salt from the advanced spent fuel conditioning process (II) : optimum immobilization condition

    Kim, Jeong Guk; Lee, Jae Hee; Yoo, Jae Hyung; Kim, Joon Hyung

    2004-01-01

    Since zeolite is known to be stable at a high temperature, it has been reported as a promising immobilization matrix for waste salt. The crystal structure of dehydrated zeolite A breaks down above 1060 K, resulting in the formation of an amorphous solid and re-crystallization to beta-Cristobalite. This structural degradation depends on the existence of chlorides. When contacted to HCl, zeolite 4A is not stable even at 473 K. The optimum consolidation condition for LiCl salt waste from the oxide fuel reduction process based on the electrochemical method (Advanced spent fuel Conditioning Process; ACP) has been studied using zeolite A since 2001. Actually the constituents of waste salt are water-soluble. And, alkali halides are known to be readily radiolyzed to yield interstitial halogens and metal colloids. For disposal in a geological repository, the waste salt must meet the acceptance criteria. For a waste form containing chloride salt, two of the more important criteria are leach resistance and waste form durability. In this work, we prepared some samples with different mixing ratios of LiCl salt to zeolite A, and then compared some characteristics such as thermal stability, salt occlusion, free chloride content, leach resistance, mixing effect, etc

  19. Durability of cemented waste in repository and under simulated conditions

    Dragolici, F.; Nicu, M.; Lungu, L.; Turcanu, C.; Rotarescu, Gh.

    2000-01-01

    The Romanian Radioactive Waste National Repository for low level and intermediate level radioactive waste was built in Baita - Bihor county, in an extinct uranium exploitation. The site is at 840 m above sea level and the host rock is crystalline with a low porosity, a good chemical homogeneity and impermeability, keeping these qualities over a considerable horizontal and vertical spans. To obtain the experimental data necessary for the waste form and package characterization together with the back-filling material behaviour in the repository environment, a medium term research programme (1996 - 2010) was implemented. The purpose of this experimental programme is to obtain a part of the data base necessary for the approach of medium and long term assessment of the safety and performance of Baita - Bihor Repository. The programme will provide: a deeper knowledge of the chemical species and reaction mechanisms, the structure, properties and performances of the final products. For safety reasons the behaviour of waste package, which is a main barrier, must be properly known in terms of long term durability in real repository conditions. Characterization of the behaviour includes many interactions between the waste package itself and the surrounding near field conditions such as mineralogy, hydrogeology and groundwater chemistry. To obtain a more deeper knowledge of the species and physical-chemical reactions participating in the matrix formation, as well as their future behaviour during the disposal period, a thorough XRD study started in 1998. For Romanian Radioactive Waste National Repository (DNDR) Baita - Bihor the following steps are planned for the conditioned waste matrix characterization in simulated and real conditions: - preparation and characterization of normal reference matrices based on different cement formulations; - preparation of reference simulated sludge cemented matrices containing iron hydroxide and iron phosphate; - selection of real and

  20. Waste conditioning for tank heel transfer. Preliminary data and results

    Ebadian, M.A.

    1999-01-01

    This report summarizes the research carried out at Florida International University's Hemispheric Center for Environmental Technology (FIU-HCET) for the fiscal year 1998 (FY98) under the Tank Focus Area (TFA) project ''Waste Conditioning for Tank Slurry Transfer.'' The objective of this project is to determine the effect of chemical and physical properties on the waste conditioning process and transfer. The focus of this research consisted in building a waste conditioning experimental facility to test different slurry simulants under different conditions, and analyzing their chemical and physical properties. This investigation would provide experimental data and analysis results that can make the tank waste conditioning process more efficient, improve the transfer system, and influence future modifications to the waste conditioning and transfer system. A waste conditioning experimental facility was built in order to test slurry simulants. The facility consists of a slurry vessel with several accessories for parameter control and sampling. The vessel also has a lid system with a shaft-mounted propeller connected to an air motor. In addition, a circulation system is connected to the slurry vessel for simulant cooling and heating. Experimental data collection and analysis of the chemical and physical properties of the tank slurry simulants has been emphasized. For this, one waste slurry simulant (Fernald) was developed, and another two simulants (SRS and Hanford) obtained from DOE sites were used. These simulants, composed of water, soluble metal salts, and insoluble solid particles, were used to represent the actual radioactive waste slurries from different DOE sites. The simulants' chemical and physical properties analyzed include density, viscosity, pH, settling rate, and volubility. These analyses were done to samples obtained from different experiments performed at room temperature but different mixing time and strength. The experimental results indicate that the

  1. Sanitation of conditioned radioactive waste after a contamination accident

    Aeppli, J.

    1980-01-01

    In June 1978, there occurred in the port of Ijmuiden, Netherlands, a contamination incident involving drums originating from Switzerkand and containing radioactive wastes intended to be dumped into the sea. The batch of 207 drums excluded from the sea-dumping action had to be sanitated for the next year dumping in such a manner, that these wastes met the international requirements and could be disposed of by sinking them into the Atlantic. As a consequence of extensive sanitation work, requiring part of the wastes to be newly conditioned and several drums to be packaged again, the total weight of the wastes ready for dumping was doubled. The total radiation exposure for the personnel that took part in the individual phases of sanitation amounted to about 10 man-rem. The main causes for this contamination incident were unusual chemical composition of the concentrate to be solidified, unsufficient quality control and a position not suitabble for transport. The measures taken after this incident intend to avoid similar occurrences in the future. (orig.) [de

  2. Testing of high-level waste forms under repository conditions

    Mc Menamin, T.

    1989-01-01

    The workshop on testing of high-level waste forms under repository conditions was held on 17 to 21 October 1988 in Cadarache, France, and sponsored by the Commission of the European Communities (CEC), the Commissariat a l'energie atomique (CEA) and the Savannah River Laboratory (US DOE). Participants included representatives from Australia, Belgium, Denmark, France, Germany, Italy, Japan, the Netherlands, Sweden, Switzerland, The United Kingdom and the United States. The first part of the conference featured a workshop on in situ testing of simulated nuclear waste forms and proposed package components, with an emphasis on the materials interface interactions tests (MIIT). MIIT is a sevent-part programme that involves field testing of 15 glass and waste form systems supplied by seven countries, along with potential canister and overpack materials as well as geologic samples, in the salt geology at the Waste Isolation Pilot Plant (WIPP) in Carlsbad, New Mexico, USA. This effort is still in progress and these proceedings document studies and findings obtained thus far. The second part of the meeting emphasized multinational experimental studies and results derived from repository systems simulation tests (RSST), which were performed in granite, clay and salt environments

  3. Release of Waste Tire Comprehensive Utilization Industry Access Conditions

    2012-01-01

    On July 31, 2012, the Ministry of Industry and Information Technology released the Tire Retread- ing lndustry Access Conditions and Waste Tire Comprehensive Utilization Industry Access Condi- tions with the No. 32 announcement of 2012. The state will lay a foundation for realizing the green, safe, efficient, eco-friendly and energy saving tar- gets in the "12th Five-year Plan" of the industry by raising access conditions, regulating industrial development order, strengthening environmental protection, promoting corporate optimizing and up- grading, improving resources comprehensive utiliza- tion technology and management level and guiding the "harmless recycling and eco-friendly utiliza- tion" of the industry.

  4. Dioxins from medical waste incineration: Normal operation and transient conditions.

    Chen, Tong; Zhan, Ming-xiu; Yan, Mi; Fu, Jian-ying; Lu, Sheng-yong; Li, Xiao-dong; Yan, Jian-hua; Buekens, Alfons

    2015-07-01

    Polychlorinated dibenzo-p-dioxins (PCDDs) and polychlorinated dibenzofurans (PCDFs) are key pollutants in waste incineration. At present, incinerator managers and official supervisors focus only on emissions evolving during steady-state operation. Yet, these emissions may considerably be raised during periods of poor combustion, plant shutdown, and especially when starting-up from cold. Until now there were no data on transient emissions from medical (or hospital) waste incineration (MWI). However, MWI is reputed to engender higher emissions than those from municipal solid waste incineration (MSWI). The emission levels in this study recorded for shutdown and start-up, however, were significantly higher: 483 ± 184 ng Nm(-3) (1.47 ± 0.17 ng I-TEQ Nm(-3)) for shutdown and 735 ng Nm(-3) (7.73 ng I-TEQ Nm(-3)) for start-up conditions, respectively. Thus, the average (I-TEQ) concentration during shutdown is 2.6 (3.8) times higher than the average concentration during normal operation, and the average (I-TEQ) concentration during start-up is 4.0 (almost 20) times higher. So monitoring should cover the entire incineration cycle, including start-up, operation and shutdown, rather than optimised operation only. This suggestion is important for medical waste incinerators, as these facilities frequently start up and shut down, because of their small size, or of lacking waste supply. Forthcoming operation should shift towards much longer operating cycles, i.e., a single weekly start-up and shutdown. © The Author(s) 2015.

  5. Procedure for conditioning high-level solidified wastes

    Hild, W; Krause, H; Scheffler, K

    1974-05-30

    The molds of glass, ceramic or basalt-similar mass in which highly radioactive wastes are incorporated are used for the conditioning of waste waters and/or of sewage or precipitating sludge or of natural water to obtain drinking water, prior to the end storage. By means of the gamma-radiation they emit, the viruses and bacteria and worm eggs are killed off as well as the poisonous, and organic substances such as, e.g., chlorated aromatics are destroyed. Furthermore, the filtration power is increased by coagulation, and the sludge is drained. Natural water is degermed. In particular, fission product mixtures of light water reactors can be incorporated in the molds. The molds are immersed in the media.

  6. Treatment and conditioning of metallic intermediate level waste

    Lidar, Per; Larsson, Arne; Huutoniemi, Tommi; Blank, Eva; Elfwing, Mattias

    2014-01-01

    In 2011 SKB started an R and D program for evaluating different disposal concepts for LL-LILW. The purpose was to develop alternative repository concepts and conditioning methods for LL-LILW and to evaluate and compare them from a range of parameters. The goal is to present a comparison between identified repository concepts by 2013. The material should be of such a quality that SKB can make decisions of which concepts that are to be further investigated in a safety analysis. As a part of the R and D program for the LL-LILW disposal facility, Studsvik was assigned to investigate whether melting of metallic LL-LILW is technically feasible and, if so, what the requirements are to build and operate such a facility. Specific concern was given to the following metallic components: - Core components and reactor internals from both boiling water reactors (BWRs) and pressurized water reactors (PWRs). - Reactor pressure vessels from PWRs. The paper presents a feasibility study of a melting facility for core components and reactor internals. An overview is given of how such a facility for treatment of intermediate level waste might be designed, constructed and operated and highlights both the possibilities and challenges. A cost estimate and a risk analysis are presented in order to make a conclusion of the technical feasibility of such a facility. Based on the Studsvik authors' experience in operating a low level waste melting facility, their conclusion is presented in the paper, considering cost of constructing and operating such a facility, in conjunction with the radio-logical risks associated with operation and the benefits to disposal and long term safety. Studsvik also investigated alternative techniques for embedding of metallic ILW components. Embedding of radioactive metallic ILW components protects the component from corrosion and leakage of radionuclides from repository to biosphere can thereby be both delayed and decreased. Conditioning by embedding has

  7. Evaluation of fourier transform profilometry performance: quantitative waste volume determination under simulated Hanford waste tank conditions

    Jang, Ping-Rey; Leone, Teresa; Long, Zhiling; Mott, Melissa A.; Perry Norton, O.; Okhuysen, Walter P.; Monts, David L.

    2007-01-01

    The Hanford Site is currently in the process of an extensive effort to empty and close its radioactive single-shell and double-shell waste storage tanks. Before this can be accomplished, it is necessary to know how much residual material is left in a given waste tank and the chemical makeup of the residue. The objective of Mississippi State University's Institute for Clean Energy Technology's (ICET) efforts is to develop, fabricate, and deploy inspection tools for the Hanford waste tanks that will (1) be remotely operable; (2) provide quantitative information on the amount of wastes remaining; and (3) provide information on the spatial distribution of chemical and radioactive species of interest. A collaborative arrangement has been established with the Hanford Site to develop probe-based inspection systems for deployment in the waste tanks. ICET is currently developing an in-tank inspection system based on Fourier Transform Profilometry, FTP. FTP is a non-contact, 3-D shape measurement technique. By projecting a fringe pattern onto a target surface and observing its deformation due to surface irregularities from a different view angle, FTP is capable of determining the height (depth) distribution (and hence volume distribution) of the target surface, thus reproducing the profile of the target accurately under a wide variety of conditions. Hence FTP has the potential to be utilized for quantitative determination of residual wastes within Hanford waste tanks. We have completed a preliminary performance evaluation of FTP in order to document the accuracy, precision, and operator dependence (minimal) of FTP under conditions similar to those that can be expected to pertain within Hanford waste tanks. Based on a Hanford C-200 series tank with camera access through a riser with significant offset relative to the centerline, we devised a testing methodology that encompassed a range of obstacles likely to be encountered 'in tank'. These test objects were inspected by use

  8. Conditioning of intermediate-level waste at Forschungszentrum Juelich GmbH

    Krumbach, H.

    2003-01-01

    This contribution to the group of low-level, intermediate, mixed and hazardous waste describes the conditioning of intermediate-level mixed waste (dose rate above 10 mSv/h at the surface) from Research Centre Juelich (FZJ). Conditioning of the waste by supercompaction is performed at Research Centre Karlsruhe (FZK). The waste described is radioactive waste arising from research at Juelich. This waste includes specimens and objects from irradiation experiments in the research reactors Merlin (FRJ-1) and Dido (FRJ-2) at FZJ. In principle, radioactive waste at Forschungszentrum Juelich GmbH is differentiated by the surface dose rate at the waste package. Up to a surface dose rate of 10 mSv/h, the waste is regarded as low-level. The radioactive waste described here has a surface dose rate above 10 mSv/h. Waste up to 10 mSv/h is conditioned at the Juelich site according to different conditioning methods. The intermediate-level waste can only be conditioned by supercompaction in the processing facility for intermediate-level waste from plant operation at Research Centre Karlsruhe. Research Centre Juelich also uses this waste cell to condition its intermediate-level waste from plant operation. (orig.)

  9. Determination of Ra-226 by gamma-ray spectrometry

    Martinez Lobo, A.

    1988-01-01

    This work deals with the method of determination of 226 Ra by low energy photon spectrometry. For this purpose, the interference due to 235 U, that emits a photon with a close energy, has to be considered. The contribution of 235 U to the 186 KeV photopeak is studied through the 63 KeV 234 Th and the 144 KeV 235 U emissions. From the minimum detectable activity of 226 Ra it is discussed the applicability of this method to several kind of samples. (Author)

  10. Past and present of risk assessment for RA-226 releases

    Paschoa, A.S.

    1982-12-01

    Some of the new concepts introduced by ICRP 26 seem to be difficult to apply to the case of dose limits concerning the 226 Ra releases from the front end of the nuclear fuel cycle. Accordingly most national legislations have not been permeated yet by the 226 Ra dose limits based on such concepts. This work calls the attention on the one hand that a loose concept of acceptable risk is implicitly used in a dose limitation system for 226 Ra when such system is based on calculating the dose as a fraction of the (MPC) sub(w) introduced earlier by the ICRP 2, and on the other hand that the ALI currently recommended by the ICRP 30 should be used only in the framework of the recommendations published in the ICRP 26, which adopts a better defined concept of risk. (Author) [pt

  11. Waste migration in shallow burial sites under unsaturated flow conditions

    Eicholz, G.G.; Whang, J.

    1987-01-01

    Unsaturated conditions prevail in many shallow-land burial sites, both in arid and humid regions. Unless a burial site is allowed to flood and possibly overflow, a realistic assessment of any migration scenario must take into account the conditions of unsaturated flow. These are more difficult to observe and to model, but introduce significant changes into projected rates of waste leaching and waste migration. Column tests have been performed using soils from the Southeastern coastal plain to observe the effects of varying degrees of ''unsaturation'' on the movement of radioactive tracers. The moisture content in the columns was controlled by maintaining various levels of hydrostatic suction on soil columns whose hydrodynamic characteristics had been determined carefully. Tracer tests, employing Cs-137, I-131 and Ba-133 were used to determine migration profiles and to follow their movement down the column for different suction values. A calculational model has been developed for unsaturated flow and seems to match the observations fairly well. It is evident that a full description of migration processes must take into account the reduced migration rates under unsaturated conditions and the hysteresis effects associated with wetting-drying cycles

  12. The conditioned reprocessing waste returns. An overview of the question

    Donato, A.

    1987-01-01

    Although the spent nuclear fuel reprocessing is at present under careful reconsideration and analysis in several countries, the economics, the environmental and health protection aspects being taken into consideration by many experts, it is nevertheless currently carried out in Great Britain and in France as a commercial service offered to the domestic utilities an to foreign customers, according to the contracts and the agreements signed in the past. Such contracts have been signed with COGEMA and/or BNFL by seven countries: Germany, Sweden, Japan, Belgium, Switzerland, Italy, Holland. As a consequence of this, a big number of high level radioactive glass containers and of cemented and bituminized waste will be returned in order to be stored and disposed off in these European countries and in Japan. The disposal of the conditioned wastes will only be possible if their characteristics comply with the acceptance criteria established or to be established in each customer country. A brief review of the situation will be presented in this paper, particular attention being given to the problems possibly arising from the acceptance point of view of the different reprocessing waste categories

  13. Evaluation of national cements for the conditioning of radioactive wastes

    Mallaupoma, M.; Soriano, A.; Rodriguez, G.; Cruz, W.

    1996-01-01

    The preliminary research studies carried out to implement the liquid radioactive waste conditioning by cementation are described. First of all, different kind of commercial cements in Peru are analyzed. In the first step, the analysis were made without using the radioactive material. The analyzed parameters were density, porosity, setting time and mechanical strength of a cement type called 'Atlas'. Samples of two geometries were used. One of them was a cylindrical sample (48mm diameter and 48mm height) and the another one was a prismatic sample (40x40x160mm). The results of the different kind of analysis are presented in this paper. (authors). 2 refs., 3 tabs

  14. Corrosion of copper under Canadian nuclear fuel waste disposal conditions

    King, F.; Litke, C.D.

    1990-01-01

    The corrosion of copper was studied under Canadian nuclear fuel waste disposal conditions. The groundwater in a Canadian waste vault is expected to be saline, with chloride concentrations from 0.1 to 1.0 mol/l. The container would be packed in a sand/clay buffer, and the maximum temperature on the copper surface would be 100C; tests were performed up to 150C. Radiation fields will initially be around 500 rad/h, and conditions will be oxidizing. Sulfides may be present. The minimum design lifetime for the container is 500 years. Most work has been done on uniform corrosion, although pitting has been considered. It was found that the rate of uniform corrosion in aerated NaCl at room temperature is limited by the rate of the anodic reaction, which is controlled mainly by the rate of transport of dissolved metal species away from the copper surface. The rate of corrosion should become controlled by the transport of oxygen to the copper surface only at very low oxygen concentrations. In the presence of gamma radiation the corrosion rate may never become cathodically transport limited. In compacted buffer material, the corrosion rate appears to be limited by the rate of transport of copper species away from the corroding surface. The authors recommend that long-term predictions of container lifetime should be based on the known rate-determining step for the overall corrosion process. 8 refs

  15. Minerals and design of new waste forms for conditioning nuclear waste

    Montel, Jean-Marc

    2011-02-01

    Safe storage of radioactive waste is a major challenge for the nuclear industry. Mineralogy is a good basis for designing ceramics, which could eventually replace nuclear glasses. This requires a new storage concept: separation-conditioning. Basic rules of crystal chemistry allow one to select the most suitable structures and natural occurrences allow assessing the long-term performance of ceramics in a geological environment. Three criteria are of special interest: compatibility with geological environment, resistance to natural fluids, and effects of self-irradiation. If mineralogical information is efficient for predicting the behaviour of common, well-known minerals, such as zircon, monazite or apatite, more research is needed to rationalize the long-term behaviour of uncommon waste form analogs.

  16. Direct measurement of γ-emitting radionuclides in waste drum

    Ma Ruwei; Mao Yong; Zhang Xiuzhen; Xia Xiaobin; Guo Caiping; Han Yueqin

    1993-01-01

    The low-level rad waste produced from nuclear power plant, nuclear facilities, and in the process of their decommissioning is stored in waste depository. For the safety of transport and storage of these wastes, some test must be done. One of them is to analyse the kinds and activities of radionuclides in each waste drum. Segmented scanning gamma spectrum analysis can be used for direct measurement of gamma-emitting radionuclides in drum. Gamma emitters such as Co-60, Cs-137, Ra-226 can be measured directly from outside of drum. A method and system for direct measuring gamma emitters in waste drum are described, and measuring apparatus and measurement results as well

  17. Food waste co-digestion with slaughterhouse waste and sewage sludge: Digestate conditioning and supernatant quality.

    Borowski, Sebastian; Boniecki, Paweł; Kubacki, Przemysław; Czyżowska, Agata

    2018-04-01

    In this study, the anaerobic mesophilic co-digestion of food waste (FW) with municipal sewage sludge (MSS) and slaughterhouse waste (SHW) was undertaken in 3-dm 3 laboratory reactors as well as in 50-dm 3 reactors operated in semi-continuous conditions. The highest methane yield of around 0.63 m 3 CH 4 /kgVS fed was achieved for the mixture of FW and SHW treated in the laboratory digester operated at solids retention time (SRT) of 30 days, whereas the co-digestion of FW with MSS under similar operating conditions produced 0.46 m 3 of methane from 1 kgVS fed . No significant differences between methane yields from laboratory digesters and large-scale reactors were reported. The conditioning tests with the digestates from reactor experiments revealed the highest efficiency of inorganic coagulants among all investigated chemicals, which applied in a dose of 10 g/kg allowed to reduce capiliary suction time (CST) of the digestate below 20 s. The combined conditioning with coagulants and bentonite did not further reduce the CST value but improved the quality of the digestate supernatant. In particular, the concentrations of suspended solids, COD as well as metals in the supernatant were considerably lowered. Copyright © 2017. Published by Elsevier Ltd.

  18. Leaching experiment of cement solidified waste form under unsaturated condition

    Wang Zhiming; Yao Laigen; Li Shushen; Zhao Yingjie; Cai Yun; Li Dan; Han Xinsheng; An Yongfeng

    2003-01-01

    A device for unsaturated leaching experiments was designed and built up. 8 different sizes, ranging from 40.2 cm 3 to 16945.5 cm 3 , of solidified waste form were tested in the experiment. 5 different water contents, from 0.15 to 0.40, were used for the experiment. The results show that the cumulative leaching fraction increases with water content when the sizes of the forms are equal to and less than 4586.7 cm 3 , for example, the ratios of the cumulative leaching fractions are between 1.24-1.41 under water content of 0.35 and 0.15 on 360 day of Teaching. It can also be seen that the cumulative leaching fraction under higher water content is close to that under saturated condition. The cumulative leaching fraction decreases with size of the form. Maximum leached depth of the solidified waste forms is about 2.25 cm after one year Teaching. Moreover, it has no clear effect on cumulative leaching fraction that sampling or non-sampling during the experiment

  19. Hydrothermal carbonization of biomass waste under low temperature condition

    Putra Herlian Eriska

    2018-01-01

    Full Text Available In this paper, the use of banana peel for energy purposes was investigated. Banana peel is a lignocellulosic waste since it is the most widely produced and consumed fruit in Indonesia. Among the others, hydrothermal carbonization (HTC was chosen as alternative themochemical process, suitable for high moisture biomass. Through a 1 L stirred reactor, hydrothermal treatments were performed under low temperature condition (190, 210 and 230 °C, residence times (30 and 60 min, and biomass to water ratio (1:3, 1:5, and 1:10. Three of product were collected from the process with primary material balance. Solid phase (hydrochar was evaluated in terms of calorific value, proximate and ultimate analysis. The results suggested that the hydrothermal carbonization of banana peel gave high heating value (HHV of 20.09 MJ/kg for its char after dried naturally.

  20. Nondestructive techniques for the control of conditioned radioactive wastes

    Delprato, U.

    1987-01-01

    The final product of the radwaste conditioning process must satisfy certain requirments and physico-chemical properties in order to assure its safe long-term behaviour. Of course, the foreseen quality assurance and quality control should be conducted by means of non-destructive techniques. This work presents an over-view of various applicable non-destructive methods of analysis, showing their fields of investigation in testing waste packages, together with some arising practical problems. The most promising methods, such as eddy current testing, ultrasonic testing, γ-scanning, γ-spectroscopy, neutron counting and computerized tomography, are treated more deeply and some applications are presented. Particular attention is devoted to the development of a device based on computerized tomography; its essential components are reported and some design problems are also discussed

  1. Hulls and structural material waste conditioning by high pressure compaction

    Frotscher, H.

    1991-01-01

    Since 1986 KfK is developing a conditioning process. Main subjects of the investigations were the development of the production technique and the planning of the most important equipments of the process under remote conditions. The process is based on an extensive program of experiments. Inactive bulks of hulls and structural material components were compacted using maximum axial pressure load of about 300 MPa. The product density as function of press force was experimentally determinated. The mechanical loads of the press and tools were estimated for the design of these equipments. The hydraulic press consists a horizontal four-cylinder press. The maximum force of the press is 25 MN. The main advantage is the modular design of the press which is open on all sides. Especially the free accessibility from top is ensured. The report also represents relevant radiological data of the alternative product. Co-60 is the dominating activity of the product due to the effects of the heat production. An amount of 10 kg hull waste or 25 kg top and bottom pieces of the spent fuel assemblies per package is already beyond the Co-60 limit of the KONRAD regulations. The nuclear thermal power of a filled container is approximately sixty times lower compared with a vitrified HLW-container. Since the product shows thermal stability beyond 200 0 C, this it is suited for a combined disposal together with vitrified HLW-containers in salt bore holes of a geological disposal. The preliminary cost evaluation is based on a reprocessing throughput of 500 t HM per year and volume reduction factor of 5.3. Accordingly there are produced 300 waste packages with hulls only or 625 units with hulls and top and bottom pieces which require 1.6 or 2.3 millions DM respectively

  2. Development of agency guidance for nuclear industry submissions for conditioning intermediate level waste

    2001-01-01

    The project was carried out by RM Consultants with the overall intention of providing the Environment Agency with a sound basis on which to develop guidance on the conditioning of intermediate level waste (ILW). Waste producers are currently in the process of retrieving and conditioning many of its ILW waste streams. This is at a time where the nature and timing of any future disposal route for these wastes is uncertain. The Agency is concerned that decisions taken on how ILW should be conditioned take into account matters of interest to the Agency, such as the future disposability of wastes, the production of secondary wastes and releases to the environment. This study provides information on the arrangements by which waste producers' proposals for the conditioning of intermediate level waste are assessed, and on the Agency's role in liaising with the Nuclear Installations Inspectorate, waste producers and Nirex. The report makes recommendations on the content and handling of waste producers' proposals in order that the Agency can satisfy itself that the environmental impact of waste conditioning and the disposability of the resultant waste packages is addressed in a timely and consistent manner

  3. New approach and methodology for radionuclide researches of oil industry wastes

    Humbatov, F.; Lisanova, E.; Suleymanov, B.; Ahmedov, M.

    2005-01-01

    Full text : Oil and gas production and processing operations sometimes accumulate Norm at elevated concentrations in by-product waste streams. The sources of most of the radioactivity are isotopes of uranium-238 (U-238) and thorium-232 (Th-232) naturally present in subsurface formations from which oil and gas are produced. The primary radionuclides of concern in NORM wastes are Ra-226 of the U-238 decay series, and Ra-228 of the Th-232 decay series. Other radionuclides of concern include radionuclides that form from the decay of Ra-226 and Ra-228. The production waste streams most likely to be contaminated by elevated radium concentrations include produced water, scale, and sludge. Spills or intentional releases of these waste streams to the ground can result in NORM-contaminated soils that must also be disposed of. Radium, which is slightly soluble, can be mobilized in the liquid phases of a formation and transported to the surface in the produced water stream. Dissolved radium either remains in solution in the produced water or precipitates out in scales or sludges. Conditions that appear to affect radium solubility and precipitation include water chemistry (primarily salinity), temperature, and pressure. NORM contamination of scale and sludge can occur when dissolved radium co precipitates with other alkaline earth elements such as barium, strontium, or calcium. In the case of scale, the radium co precipitates, primarily with barium, to form hard, insoluble sulfate deposits. Scale typically forms on the inside of piping, filters, injection wellhead equipment, and other water handling equipment, but also can form as a coating on produced sand grains. In the case of sludge, radium can be present in several forms. It can co precipitate with silicates and carbonates that form in the sludge, or it can be present in pieces of barium sulfate scale that become incorporated into the sludge. NORM-contaminated sludges can accumulate inside piping, separators, heater

  4. Qualification of R.A. waste conditioning process and installations by ONDRAF/NIRAS

    Havard, P.; Faniel, L.; Voet, M.; Goeyse, A. de.

    1993-01-01

    ONDRAF/NIRAS in its role of national agency responsible for the management of radioactive waste in Belgium (including transport, intermediate storage and final disposal of the conditioned waste) has defined and enforces conditions for the acceptance (i.e. taking over) of conditioned waste packages. The waste acceptance conditions applicable at the present time are: 1. The conditioning process and installations are qualified by ONDRAF/NIRAS; 2. The waste packages are produced according to the qualified process and installations, and meet the technical specifications and acceptance criteria defined by ONDRAF/NIRAS; 3. The production of the waste packages is supervised by ONDRAF/NIRAS through an inspection and control programme specific to each conditioning process and associated installation, and has been found satisfactory. (author)

  5. Long-term environmental assessment of waste from PyroGreen system

    Ju, Heejae; Hahm, Inhye; Sohn, Sungjune; Hwang, Il-Soon

    2016-01-01

    We have conducted a long-term environmental assessment of a geological repository for Intermediate Level Wastes (ILW) arising from PyroGreen processes that has been developed to decontaminate all HLW from the pyrochemical partitioning of spent nuclear fuels (SNF). PyroGreen process has been designed so that final ILW can meet conservative acceptance criteria such as one established for the Waste Isolation Pilot Plant (WIPP) in U.S.A. The nuclide inventory of final vitrified PyroGreen waste is calculated using ORIGEN 2.1 based on the design decontamination factor of PyroGreen processes applied to 18,171 metric tons of PWR SNF with 45 GWD/MTU burnup. Using GoldSim model, the environmental impact of ILW upon geological disposal at an intermediate depth. Among radioactive nuclides, Ra 226 , Rn 222 and Sn 126 are identified as key contributors to radiological dose for general public. The environmental impact of PyroGreen wastes satisfies the Korean dose limit of 0.1 mSv/year with sufficiently high margin. Sensitivity studies have shown that the predicted dose can vary significantly by distribution coefficient of Ra 226 and Rn 222 , solubility limit of Se 79 . (authors)

  6. Conditioning of Radioactive Wastes Prior to disposal; Segregation and Repackaging

    Kang, Il Sik; Kim, Ki Hong; Hong, Dae Seok; Lee, Bum Chul [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-05-15

    We stored several types of radioactive wastes at interim storage facility of KAERI ; the combustible wastes (cloths, decontamination paper and vinyls) from Hanaro multipurpose research reactor, nuclear fuel cycle facility, RI production facility and laboratories, and the non-combustible wastes (metals and glass) dismantled and discarded from the apparatus of laboratories which deteriorated, and also the miscellaneous wastes (spent air-filters). After a segregation of these wastes as the same type, they were treated by using a proper method in order to meet both the national regulation and the waste acceptance criteria of Kyung-ju disposal site. For a safe disposal of waste drums, the waste characterization system including a scaling factor which is hard to measure special radionuclides is established completely. All data of those repackaged drums were input into an ANSIM system so that we could manage them clearly and effectively such like an easy transparent traceability. Through a decontamination of empty drums generated in a repackaging process of the stored drums, these drums can be reused or compressed to reduce their volume reduction for disposal. As a result, the space to store radioactive waste drums are secured more than before, and also the interim storage facility are maintained in a good state. The combustible wastes, which stored at the interim storage facility of KAERI, are managed safely in compliance with the specifications of the national regulations and disposal site. Through the classification and repackage of them, the storage space of drums at RWTF was secured more than before, and the storage facility was kept in a good state, and also the disposal cost of all stored waste drums of KAERI will be reduced due to the reduction of waste volume. Base on the experiences, the non-combustible wastes will be treated soon.

  7. 78 FR 64905 - Carriage of Conditionally Permitted Shale Gas Extraction Waste Water in Bulk

    2013-10-30

    ...-ZA31 Carriage of Conditionally Permitted Shale Gas Extraction Waste Water in Bulk AGENCY: Coast Guard... availability of a proposed policy letter concerning the carriage of shale gas extraction waste water in bulk... transport shale gas extraction waste water in bulk. The policy letter also defines the information the Coast...

  8. Survey of stores for conditioned intermediate and low level wastes in Europe

    1985-10-01

    A survey has been conducted of eleven waste storage facilities in six countries. Wastes considered are intermediate and low level, conditioned for disposal. Civil engineering, handling facilities, container type, waste activities, doses to the public and to operators are considered. (author)

  9. Effluents from a waste rock deposit of a former uranium mine in Saxony/Germany - Mass flow balance of water and dissolved solids

    Biehler, D.

    2002-01-01

    Soon after uranium mining had ceased in eastern Germany in 1990, work for remediation of several mining sites began. The Wismut GmbH, owner of the Mine of Dresden-Gittersee's waste rock dump, introduced the concept of reducing the impact to the environment via water and air paths by implementing a multi-layer soil cover. The deposit consists mainly of waste rock (clastic sediments of Doehlener Becken, deep metamorphic rocks) but also of low-grade ore (U-rich coal) and tailing materials. At the time when remediation started, the effluents completely infiltrated the underground. Because of previous surface exfiltration activities, they were already known to be very rich in dissolved solids, especially in sulphate and uranium. As demanded by the state authorities, the owner funded a vast hydrogeological study of the site. In testing the efficiency of surface sealing, the study indicated a mass flow balance of water and dissolved solids for the current situation, and predicted emissions into the water path which would occur after realisation of the proposed soil cover. The field investigation program consisted of: measurements of flow, of concentrations of dissolved solids (esp. U and Ra-226) and of contents of environmental isotopes in precipitation, surface runoff, seepage water and groundwater in the current condition of the dump; the study of waste rock material (geochemistry, mineralogy); waste rock material elution tests; underground investigation by drilling boreholes up to 270 m in depth. The resulting data allowed for: a hydrogeological conceptual model of the site; a consistent mass flow balance for the current condition of the dump; a prediction of concentrations in groundwater resulting after the realisation of a soil cover. The predictions show that the concentrations of dissolved solids in the contaminated groundwater would be significantly decreased. Furthermore it would be possible to reach the standards for drinking water with respect to uranium

  10. Strategy for research on radioactive waste processing and conditioning in France

    Cavedon, J.M.; Tallec, M.

    2001-01-01

    Research on radioactive medium level waste processing and conditioning aims at offering processing routes for waste forms and materials of potential value that are not yet provided easy handling by existing industrial processes. These studies are mandatory under the Dec 31, 1991 law and are coordinated by CEA. The strategy relies on the completion and rationalization of the existing processing routes, within acceptable technical and economic limits. Waste processing techniques aim at reducing the volume and the chemical diversity of medium activity waste, and are based on incineration-vitrification. Conditioning techniques call for high performance matrices and standardized containers, the latter keeping an ability to contain bulk waste. (author)

  11. Current situation of management of radioactive wastes in the Instituto de Engenharia Nuclear, Brazil

    Zidan, Priscila M.; Silva, Joao C.P.; Echternacht, Marcus V.

    2000-01-01

    As its own legal responsibility, Nuclear Engineering Institute - IEN has received radioactive wastes generated in Rio de Janeiro and Espirito Santo states. But, from July 1997 to June 1999, IEN was not able to receive wastes because of the lack of space in the temporary repository. Recent studies show that increasing the treatment facilities could contribute to optimize the disposal of wastes. According to National Commission of Nuclear Energy resolutions, IEN was several times requested for discarding of lightning rods containing Am-241 and Ra-226. This fact motivated IEN to look for options to make possible the receiving of wastes until a new deposit were built. A temporary place was prepared and since last July it has been receiving wastes again. In this paper it is described the current structure of radioactive waste management at IEN, objectives and goals to be reached until December 2000. (author)

  12. Analysis of contamination conditions of the Joyo Waste Treatment Facility

    Yoshizawa, S.; Ishijima, N.; Tanimoto, K.

    1999-08-01

    Decontamination methods have been studied for decommissioning of Joyo Waste Treatment Facility whose operation has been stopped in 1994. In this study, we analyzed samples of its system piping, whose dose rate was relatively low, to determine conditions of contamination. We also study appropriate decontamination methods for them. Results are as follows. 1. The inner surfaces of piping were covered with a very thin clad that was less than 1 micrometer in thickness and had many vacancies, looked like particle detachment, which were about 20 micrometers in depth. Something like corrosion product was observed near the surface and it was 440 micrometers in depth. 2. Radioactive contamination was considered to settle on a lower part of the piping and to be buried in the clad. A kind of dominant contamination nuclide was 60 Co. 3. Hot nitric acid process will be suitable for system decontamination to reduce dose rate before dismantling. But its feasibility tests are indispensable using samples of main system components that have high dose rate. Rubber lining tanks requires another methods because of its difficulty of decontamination. 4. Analyses and decontamination tests using main system are required to decide through decontamination methods according to the clearance level. (author)

  13. Low Level Waste Conceptual Design Adaption to Poor Geological Conditions

    Bell, J.; Drimmer, D.; Giovannini, A.; Manfroy, P.; Maquet, F.; Schittekat, J.; Van Cotthem, A.; Van Echelpoel, E.

    2002-01-01

    Since the early eighties, several studies have been carried out in Belgium with respect to a repository for the final disposal of low-level radioactive waste (LLW). In 1998, the Belgian Government decided to restrict future investigations to the four existing nuclear sites in Belgium or sites that might show interest. So far, only two existing nuclear sites have been thoroughly investigated from a geological and hydrogeological point of view. These sites are located in the North-East (Mol-Dessel) and in the mid part (Fleurus-Farciennes) of the country. Both sites have the disadvantage of presenting poor geological and hydrogeological conditions, which are rather unfavorable to accommodate a surface disposal facility for LLW. The underground of the Mol-Dessel site consists of neogene sand layers of about 180 m thick which cover a 100 meters thick clay layer. These neogene sands contain, at 20 m depth, a thin clayey layer. The groundwater level is quite close to the surface (0-2m) and finally, the topography is almost totally flat. The upper layer of the Fleurus-Farciennes site consists of 10 m silt with poor geomechanical characteristics, overlying sands (only a few meters thick) and Westphalian shales between 15 and 20 m depth. The Westphalian shales are tectonized and strongly weathered. In the past, coal seams were mined out. This activity induced locally important surface subsidence. For both nuclear sites that were investigated, a conceptual design was made that could allow any unfavorable geological or hydrogeological conditions of the site to be overcome. In Fleurus-Farciennes, for instance, the proposed conceptual design of the repository is quite original. It is composed of a shallow, buried concrete cylinder, surrounded by an accessible concrete ring, which allows permanent inspection and control during the whole lifetime of the repository. Stability and drainage systems should be independent of potential differential settlements an d subsidences

  14. A mathematical model for the performance assessment of engineering barriers of a typical near surface radioactive waste disposal facility

    Antonio, Raphaela N.; Rotunno Filho, Otto C. [Universidade Federal, Rio de Janeiro, RJ (Brazil). Coordenacao dos Programas de Pos-graduacao de Engenharia. Lab. de Hidrologia e Estudos do Meio Ambiente]. E-mail: otto@hidro.ufrj.br; Ruperti Junior, Nerbe J.; Lavalle Filho, Paulo F. Heilbron [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil)]. E-mail: nruperti@cnen.gov.br

    2005-07-01

    This work proposes a mathematical model for the performance assessment of a typical radioactive waste disposal facility based on the consideration of a multiple barrier concept. The Generalized Integral Transform Technique is employed to solve the Advection-Dispersion mass transfer equation under the assumption of saturated one-dimensional flow, to obtain solute concentrations at given times and locations within the medium. A test-case is chosen in order to illustrate the performance assessment of several configurations of a multi barrier system adopted for the containment of sand contaminated with Ra-226 within a trench. (author)

  15. A mathematical model for the performance assessment of engineering barriers of a typical near surface radioactive waste disposal facility

    Antonio, Raphaela N.; Rotunno Filho, Otto C.

    2005-01-01

    This work proposes a mathematical model for the performance assessment of a typical radioactive waste disposal facility based on the consideration of a multiple barrier concept. The Generalized Integral Transform Technique is employed to solve the Advection-Dispersion mass transfer equation under the assumption of saturated one-dimensional flow, to obtain solute concentrations at given times and locations within the medium. A test-case is chosen in order to illustrate the performance assessment of several configurations of a multi barrier system adopted for the containment of sand contaminated with Ra-226 within a trench. (author)

  16. Radium and radon isotope investigations as tool for aquifer diagnostics considering the geochemical and hydrochemical conditions in the ground water aquifer; Radium- und Radon-Isotopen-Untersuchungen als Hilfsmittel fuer die Aquiferdiagnose unter besonderer Beruecksichtigung der geochemischen und hydrochemischen Verhaeltnisse im Grundwasserleiter

    Hurst, Stephanie

    2014-12-12

    The thesis was aimed to the development of methods for enhanced interpretation of the hydraulic conditions in a groundwater aquifer based on the determination of the Rn-222/Ra-226 ration. Further investigations concerned rocks and rock surfaces (secondary minerals) with respect to the solubility and the mobility of radium in the ground water. The samples were withdrawn in the region of the continental deep borehole (KTB Oberpfalz) and the Czech Republic (Egergraben).

  17. 78 FR 46447 - Conditional Exclusions From Solid Waste and Hazardous Waste for Solvent-Contaminated Wipes

    2013-07-31

    ... section 307 of the Clean Water Act (CWA)); A municipal solid waste landfill that is regulated under 40 CFR... laundries and dry cleaners could dispose of sludge from cleaning solvent-contaminated wipes in solid waste landfills if the sludge does not exhibit a hazardous waste characteristic. \\8\\ The Agency stated in the...

  18. Waste management from reprocessing: a stringent regulatory requirements for high quality conditioned residues

    Bordier, J. C.; Greneche, D.; Devezeaux, J. G.; Dalcorso, J.

    2000-01-01

    Nuclear waste production and management in France is governed by safety requirements imposed to all operators. French nuclear safety relies on two basic principles: · Responsibility of the nuclear operator, which expands to waste generated, · Safety basic objectives issued by national Safety Authority. For a long time the regulatory framework for waste production and management has been satisfactorily applied and has benefited to each actor of the process. LLW/MLW and HLW nuclear waste are currently conditioned in safe matrices or packages either likely to be disposed in surface repositories or designed with the intention to be disposed underground according to their radioactive content. France is looking into the case of VLLW and has already carried out a design for future disposal, the design being in the pipe. Other types of waste (i. e. radium bearing waste, graphite, and tritium content waste) are also considered in the whole framework of French waste management. (author)

  19. Crevice corrosion of titanium under nuclear fuel waste conditions

    Ikeda, B.M.; Bailey, M.G.; Clarke, C.F.; Shoesmith, D.W.

    1989-11-01

    This report describes our experimental program to investigate the localized corrosion of ASTM Grade-2 titanium. In particular, it describes the study of the crevice corrosion of titanium, the process most likely to lead to the failure of nuclear waste containers constructed from this material. The basic mechanisms of crevice corrosion are discussed in detail. This is followed by a description of our laboratory program and the various immersion tests being performed under irradiated conditions. Experiments and tests were performed in NaCl solutions (generally 1.6 wt.%) and in simulated groundwater at 100 or 150 degrees C. A mechanism for crevice corrosion of titanium is presented and justified experimentally using an electrochemical approach. During the initiation stage, the crevice reaction is controlled by the kinetics of the anodic process. As oxygen is consumed in the propagation step, control switches to the cathodic step. Crevice corrosion eventually stops when the oxygen concentration falls to a low value. Propagation of the crevice can be restarted by the addition of oxygen. Our preliminary results on the effect of varying the iron content of the titanium are presented. An increase in iron content from 0.02 wt.% to 0.13 wt.% leads to passivation, as opposed to propagation, of the crevice. The effects of γ-irradiation, temperature, and oxygen concentration are also briefly discussed. Although our conclusions must be considered tentative, the effects of γ-irradiation appear to be beneficial. some crevice corrosion rates from longer-term immersion tests are also presented. Generally the rates are very low

  20. Scientific basis for long-term prediction of waste-form performance under repository conditions

    Mendel, J.E.

    1982-10-01

    This paper presents an overview of the fundamental principles involved in predicting long-term performance of waste forms by the as-low-as-reasonably-achievable approach. Repository conditions which make up the waste-form environment, the aging of the waste form, the important radionuclides in the waste form, the chemistry of repository fluids, and multicomponent interactions testing were considered in order to describe these principles. The need for confidence limits on the prediction of waste-form performance and ways of achieving a definition of the confidence limits are discussed

  1. Classification of radioactive waste and determination of waste specifications as well as conditions of acceptance for ultimate storage

    Merz, E.

    1983-04-01

    The determination of waste specification and conditions of acceptance must follow a certain scheme, the basics of which will be presented. First the types of waste and the ultimate storage facilities will be characterized. The various categories of waste will be listed in a universally valid system, and the preliminary conditioning options will be determined. Based on the results of safety analysis taking into account the whole system - geological circumstances, ultimate store mines, types and forms of waste - specifications for the various ultimate store products are to be derived following iterative methods. Suggestions though not of a binding nature and probably subject to eventual revisions in part will be presented. To ensure the safety goals, i.e. the exclusion of radioactivity from the human biosphere, appropriate quality control is required concerning the production and the acceptance at the ultimate store. The guiding principles to be heeded will be discussed in brief. (orig./HP) [de

  2. Plate waste of adults in the United States measured in free-living conditions.

    Brian E Roe

    Full Text Available We analyze food-item level data collected from 50 adults from the United States using the Remote Food Photography Method® to provide the first estimates of plate waste gathered from adults across multiple consecutive meals and days in free-living conditions, and during laboratory-based meals with fixed food items and quantities. We find average plate waste in free-living conditions is 5.6 grams (7.7 kcals per item and that 3.3% of all food selected is returned as plate waste, where the percent waste figure is substantially lower than previously published plate waste estimates gathered primarily from dine-out settings in the United States such as buffets and institutional settings with limited-choice meals (e.g., school cafeterias. Plate waste from the same participants during the laboratory-based meals is significantly higher with an average of 203.2 grams of solid plate waste per meal (531.3 kcals or 39.1% of the food provided, which is similar to the plate waste percentages found reported in some school cafeteria settings. The amount of plate waste generated in free-living conditions is significantly positively associated with portion size selected for an item. In a multivariate analysis that controls for macronutrient profile, items selected from the vegetables, fats/oils/dressings, and grains categories are associated with significantly greater amounts of plate waste per item. We find no significant associations between free-living plate waste and gender, age, race or body mass index but find that women leave more plate waste in the lab meal where portion sizes are pre-determined by the researcher and similar for all respondents. We discuss possible implications of these findings for programs focused on reducing plate waste and food waste among consumers.

  3. Plate waste of adults in the United States measured in free-living conditions

    Allen, H. Raymond

    2018-01-01

    We analyze food-item level data collected from 50 adults from the United States using the Remote Food Photography Method® to provide the first estimates of plate waste gathered from adults across multiple consecutive meals and days in free-living conditions, and during laboratory-based meals with fixed food items and quantities. We find average plate waste in free-living conditions is 5.6 grams (7.7 kcals) per item and that 3.3% of all food selected is returned as plate waste, where the percent waste figure is substantially lower than previously published plate waste estimates gathered primarily from dine-out settings in the United States such as buffets and institutional settings with limited-choice meals (e.g., school cafeterias). Plate waste from the same participants during the laboratory-based meals is significantly higher with an average of 203.2 grams of solid plate waste per meal (531.3 kcals) or 39.1% of the food provided, which is similar to the plate waste percentages found reported in some school cafeteria settings. The amount of plate waste generated in free-living conditions is significantly positively associated with portion size selected for an item. In a multivariate analysis that controls for macronutrient profile, items selected from the vegetables, fats/oils/dressings, and grains categories are associated with significantly greater amounts of plate waste per item. We find no significant associations between free-living plate waste and gender, age, race or body mass index but find that women leave more plate waste in the lab meal where portion sizes are pre-determined by the researcher and similar for all respondents. We discuss possible implications of these findings for programs focused on reducing plate waste and food waste among consumers. PMID:29444094

  4. Experience and projects concerning treatment, conditioning and storage of all radioactive wastes from Tokai reprocessing plant

    Fukuda, G.; Matsumoto, K.; Miyahara, K.

    1984-01-01

    The active operation of Tokai reprocessing plant started in September 1977, and about 170 t U of spent fuel were reprocessed between then and December 1982. During this period, the low-level waste processing plant reduced the amount of radioactivity discharged into the environment. For radioactive liquid waste, the treatment procedures consist mainly of evaporation to keep the discharge into the sea at a low level. For combustible low-level solid waste and the solvent waste, which is of low tributyl phosphate content, incineration has been used successfully (burned: about 150 t of combined LLSW, about 50 m 3 of solvent waste, i.e. diluent waste). Most of the past R and D work was devoted to reducing the activity discharged into the environment. Current R and D work is concerned with the treatment of solvent waste, the conditioning of solid wastes, the bituminization of low-level liquid waste and the vitrification of high-level liquid waste. The paper describes present practices, R and D work and future aspects of the treatment, conditioning and storage of all radioactive wastes from Tokai reprocessing plant. (author)

  5. Conditioning of radioactive waste from the waste collection centers of the German states as illustrated by radioactive waste from industrial production processes

    Stellmacher, J.; Sickert, T.

    2011-01-01

    The amount of negligible heat generating waste in Germany is increasing due to deconstruction of decommissioned nuclear facilities. Until 2040 277.000 m 3 are expected. By conditioning processes the wastes are transferred into a chemical stabile and water insoluble state and packaged in appropriate containers for final repository disposal. The radioactive waste in the collection containers are coated with wax for immobilization of the surface contamination, in the next step the containers are filled with pressurized geopolymer, a thixotropic fluid (under pressure the viscosity is decreased, so that cavities are filled). The conditioned material, the so called interim product is stored in trays for the final packaging in appropriate containers.

  6. Thermal operations conditions in a national waste terminal storage facility

    1976-09-01

    Some of the major technical questions associated with the burial of radioactive high-level wastes in geologic formations are related to the thermal environments generated by the waste and the impact of this dissipated heat on the surrounding environment. The design of a high level waste storage facility must be such that the temperature variations that occur do not adversely affect operating personnel and equipment. The objective of this investigation was to assist OWI by determining the thermal environment that would be experienced by personnel and equipment in a waste storage facility in salt. Particular emphasis was placed on determining the maximum floor and air temperatures with and without ventilation in the first 30 years after waste emplacement. The assumed facility design differs somewhat from those previously analyzed and reported, but many of the previous parametric surveys are useful for comparison. In this investigation a number of 2-dimensional and 3-dimensional simulations of the heat flow in a repository have been performed on the HEATING5 and TRUMP heat transfer codes. The representative repository constructs used in the simulations are described, as well as the computational models and computer codes. Results of the simulations are presented and discussed. Comparisons are made between the recent results and those from previous analyses. Finally, a summary of study limitations, comparisons, and conclusions is given

  7. Waste to energy plant operation under the influence of market and legislation conditioned changes

    Tomic, Tihomir; Dominkovic, Dominik Franjo; Pfeifer, Antun

    2017-01-01

    , waste-to-energy plants need to be adapted to market operation. This influence is tracked by the gate-fee volatility. The operation of the waste-to-energy plant on electricity markets is simulated by using EnergyPLAN and heat market is simulated in Matlab, based on hourly marginal costs. The results have......In this paper, gate-fee changes of the waste-to-energy plants are investigated in the conditions set by European Union legislation and by the introduction of the new heat market. Waste management and sustainable energy supply are core issues of sustainable development of regions, especially urban...... areas. These two energy flows logically come together in the combined heat and power facility by waste incineration. However, the implementation of new legislation influences quantity and quality of municipal waste and operation of waste-to-energy systems. Once the legislation requirements are met...

  8. Research programme on the conditioning of nuclear power waste

    Hultgren, Aa.

    1981-01-01

    Main parts of this programme have included the use of zeolites and titanates to improve reactor waste treatment, the fractionation of high level reprocessing waste by extraction, and a study of liquid partition chromotographic technique for the removal of impurities from reactor cooling circuits. Preparation of large crystal zeolites has been continued and refined. For titanate production new routes are tried to produce material of a form suitable for use in a sorption process. The possibility of lithium-7 recovery from spent PWR resins in the elution process is under study. Final products from different routes of heat treatment of loaded zeolites and titanates are characterized and compared. In parallell to this work a full-scale system is under study including transport, system design, integrated process flowsheets and cost estimates. The aim is to have basis early in 1982 to decide on the merits of a plant at the planned repository for low and medium level waste (SFR), to be commissioned around 1990. In the high level waste fractionation project, a demonstration of the developed process has been performed on a fission product solution from the reprocessing of low burn-up fuel. Disregarding some equipment malfunction the design goal of better than 99.99 % actinide removal from the high level waste waste solution was reached. The basic chemistry of the process seems to be quite tolerant against reasonable flow rate deviations in the extraction cycles. Also the concluding sorption step on mordenite-titanate worked quite well. The small scale experiments on liquid partition chromatographic techniques have included studies of the capacity of various carrier materials treated with NH 4 DEHP or Aliquat-336 to sorb radioactive impurities from reactor water, both in the laboratory and at the Ringhals-1 BWR. (author)

  9. ''FIXBOX'' - a new technique for the reliable conditioning of plutonium waste solutions

    Bruchertseifer, H.; Sommer, E.; Steinemann, M.; Bart, G.

    1994-01-01

    ''FIXBOX'' - A new technique and facility for the conditioning of plutonium waste solutions has been developed and brought into operation in the Hot-laboratory at PSI, for the solidification of the waste from the research programmes. The facility is situated in glove-boxes for handling alpha activity and gamma-shielded for conditioning of fission product-containing waste. This report gives a brief description of the FIXBOX facility, the procedure and the first results of the cementation of plutonium waste solutions. As a result of this solidification, the actinide waste is homogeneous and strongly bound in the cement. The presence of gluconic acid and other complexing agents in the waste solution will not disturb this process. (author) figs., tabs., refs

  10. Long-term durability experiments with concrete-based waste packages in simulated repository conditions

    Ipatti, A.

    1993-03-01

    Two extensive experiments on long-term durability of waste packages in simulated repository conditions are described. The first one is a 'half-scale experiment' comprising radioactive waste product and half-scale concrete containers in site specific groundwater conditions. The second one is 'full-scale experiment' including simulated inactive waste product and full-scale concrete container stored in slowly flowing fresh water. The scope of the experiments is to demonstrate long-term behaviour of the designed waste packages in contact with moderately concrete aggressive groundwater, and to evaluate the possible interactions between the waste product, concrete container and ground water. As the waste packages are made of high-quality concrete, provisions have been made to continue the experiments for several years

  11. Viimsi water treatment plant for Ra removal: NORM residue/waste generation, radiation safety issues, and regulatory response

    Kiisk, M.; Suursoo, S.; Realo, E.; Jantsikene, A.; Lumiste, L.; Vaeaer, K.; Isakar, K.; Koch, R. [University of Tartu (Estonia)

    2014-07-01

    In early 2012, the first large-scale water treatment plant, specifically designed to remove Ra-isotopes from groundwater, was commissioned in Viimsi parish, North-Estonia. The plant serves approximately 15 000 consumers with maximum production capacity of 6000 m{sup 3}/d. The chosen water treatment technology is chemical free and is based on co-precipitation and adsorption with Fe(OH){sub 3} and MnO{sub 2} flocks, and adsorption of residual Ra onto zeolite sand. The chosen technology is a complex approach and is designed to reduce high Fe and Mn concentrations as well as dissolved gases along with Ra isotopes. It is proved to be well adapted with hydro-chemical conditions of the groundwater feeding the plant. As the novel technology has been applied for the first time on a large scale, the plant was taken under long-term investigation when commissioned. The latter focuses on three areas: Ra removal efficiency and its dynamics, build-up of radioactive waste, and radiation safety. The average Ra-226 and Ra-228 activity concentrations in raw water feeding the plant are approximately 0.5 Bq/L and 0.6 Bq/L, respectively, resulting in total indicative dose of 0.4 mSv/y. Operating conditions of the plant are restricted by the established indicative value of 0.1 mSv/y for drinking water, i.e. a minimum 75% removal efficiency for Ra is required. Results of the studies show that the plant operates at Ra-removal efficiency of 98% or higher without the need of regeneration or replacement of filtering materials within the first two years. Measurements confirm that ∼90% of Ra accumulates in the solid filter media, 8-9% is washed out by backwash system as liquid effluent and 1-2% is fed on to the consumer distribution network. It has been calculated that at the level of current production capacity (below 3000 m{sup 3}/d) the yearly accumulation rate in the plant is approximately 300 and 400 MBq/y for Ra-226 and Ra-228, respectively. These values strongly exceed the exemption

  12. Researches on the radioactive wastes management: advances in the domain of the conditioning and the storage

    2003-12-01

    This paper presents in the first part the researches in the domain of the radioactive wastes management at the Cea: separation processes and transmutation, the underground geologic disposal, the conditioning and the storage. The recent progresses in the domain of the conditioning and the storage are then detailed and the legal context presented. A special attention is given to the CECER of Marcoule, the expertise center on the conditioning and the storage of radioactive wastes. (A.L.B.)

  13. Ventilation and air conditioning system in waste treatment and storage facilities

    Kinoshita, Hirotsugu; Sugawara, Kazushige.

    1987-01-01

    So far, the measures concerning the facilities for treating and storing radioactive wastes in nuclear fuel cycle in Japan were in the state which cannot be said to be sufficient. In order to cope with this situation, electric power companies constructed and operated radioactive waste concentration and volume reduction facilities, solid waste storing facilities for drums, high level solid waste storing facilities, spent fuel cask preserving facilities and so on successively in the premises of nuclear power stations, and for the wastes expected in future, the research and the construction plan of the facilities for treating and storing low, medium and high level wastes have been advanced. The ventilation and air conditioning system for these facilities is the important auxiliary system which has the mission of maintaining safe and pleasant environment in the facilities and lowering as far as possible the release of radioactive substances to outside. The outline of waste treatment and storage facilities is explained. The design condition, ventilation and air conditioning method, the features of respective waste treatment and storage facilities, and the problems for the future are described. Hereafter, mechanical ventilation system continues to be the main system, and filters become waste, while the exchange of filters is accompanied by the radiation exposure of workers. (Kako, I.)

  14. E-waste management challenges in Iran: presenting some strategies for improvement of current conditions.

    Taghipour, Hassan; Nowrouz, Parviz; Jafarabadi, Mohamad Asghari; Nazari, Jalil; Hashemi, Ahmad Asl; Mosaferi, Mohammad; Dehghanzadeh, Reza

    2012-11-01

    E-waste is one of the fastest-growing waste streams in Iran, owing to an increase in consumption of electrical and electronic equipment. Nevertheless, as is the case in some other countries, E-waste management has not received sufficient attention. For the successful implementation of any waste management plan (including an E-waste management plan), the availability of sufficient and accurate information on the quantities and composition of the waste generated and on current management conditions is a fundamental prerequisite. At present, in Iran, there is no available and accurate information that describes the characteristics and generation rate of E-waste or the actual practice of management and handling of the waste. For this initial study, eight electronic products were selected for the determination of their E-waste generation rate in the country, and two cities, Tehran and Tabriz, were selected for assessment of the current condition of E-waste management. The study found that the amount of E-waste generation in the country for the eight selected electronic items alone was 115,286, 112,914 and 115,151 metric tons in 2008, 2009 and 2010, respectively. Of the types of electronic items included in the study, televisions, with an average of 42.42%, and PCs, with an average of 32.66% accounted for the greatest proportions of the total mass of E-waste generated during 2008-2010. Currently, despite the fact that primary legislation for E-waste management (as part of general waste legislation) exists in Iran, this primary legislation has not yet been implemented. In practical terms, there is no definite policy or plan for the allocation of funds to prepare suitable equipment and facilities for the management and recycling of E-waste at the end of the products' useful life. Proposed improvements in current conditions are identified, first by considering other countries' experiences and then suggesting specific practical policies, rules, and regulations that should be

  15. EVALUATION OF WASTE PACKAGE EXTERNAL ENVIRONMENTAL CONDITION STUDY

    E. N. Lindner and E. F. Dembowski

    1998-01-01

    The U. S. Department of Energy (DOE) is studying Yucca Mountain as the possible site for a permanent underground repository for disposal of spent nuclear fuel (SNF) and other high-level waste (HLW). The emplacement of high-level radioactive waste in Yucca Mountain will release a large amount of heat into the rock above and below the repository. Due to this heat, the rock temperature will rise, and then decrease when the production of decay heat falls below the rate at which heat escapes from the hot zone. In addition to raising the rock temperature, the heat will vaporize water, which will condense in cooler regions. The condensate water may drain back toward the emplacement drifts or it may ''shed'' through the pillars between emplacement drifts. Other effects, such as coupled chemical and mechanical processes, may influence the movement of water above, within, and below the emplacement drifts. This study examined near field environmental parameters that could have an effect on the waste package, including temperature, humidity, seepage rate, pH of seepage, chemistry (dissolved salts/minerals) of seepage, composition of drift atmosphere, colloids, and biota. This report is a Type I analysis performed in support of the development of System Description Documents (SDDs). A Type I analysis is a quantitative or qualitative analysis that may fulfill any of a variety of purposes associated with the Monitored Geologic Repository (MGR), other than providing direct analytical support for design output documents. A Type I analysis may establish design input, as defined in the ''Quality Assurance Requirements and Description'' (QARD) (DOE 1998). This study establishes a technical basis for emplacement drift (i.e. at the waste package surface) environment criteria to be considered in the development of the waste package design. The information will support development of several SDDs and resolve emplacement drift external environment questions in the criteria of those

  16. Radioactivity measurements in the vicinity of the mine waste heap at Crossen and radiation dose assessment; Radioaktivitaetsmessungen in der Umgebung der Bergehalde Crossen und Abschaetzung der Strahlenexposition

    Kulzer, R.

    1998-09-01

    The radiation dose to the population living in the vicinity of the mine waste heap is assessed. The measurements carried out were to verify the dose relevance of ambient radioactivity on site, in particular the ingestion and inhalation pathways and the external exposure pathways. The nuclide Pb-210 was used as an indicator because of its large dose factor for assessment of ingestion and its airborne dispersion as an Rn-222 daughter product. The waste heap material releases large quantities of this nuclide. Ingestion of radioactivity from the waste heap may be caused by wind-borne erosion and activity deposition on plants in the area. Thererfore, the specific activities of Pb-210 and Ra-226 have been measured in soil and plant specimens sampled at various distances from the waste heap. (orig./CB) [Deutsch] Die Strahlenexposition der in der Naehe einer Bergehalde lebenden Bevoelkerung wird bestimmt. Zu diesem Zweck wurden Messungen realisiert, die den Ingestions- und Inhalationspfad sowie die externe Exposition fuer die vorgefundene Situation auf ihre Dosisrelevanz ueberpruefen sollten. Hierzu diente das Nuklid Pb-210 mit seinem grossen Dosisfaktor fuer die Ingestion und seiner besonderen Verbreitungsmoeglichkeit ueber die Luft als Tochter von Rn-222. Dieses wird aus dem Haldenmaterial in grossen Mengen freigesetzt. Haldenmaterial kann ueber den Ingestionspfad in den menschlichen Koerper aufgenommen werden, wenn es durch Winderosion auf Pflanzenoberflaechen in der Umgebung abgelagert wird.Deshalb wurden die spezifischen Aktivitaeten an Pb-210 und Ra-226 von Boden- und Pflanzenproben in verschiedenen Entfernungen zur Halde bestimmt.

  17. Study on sampling conditions for the monitoring of waste air

    Moeller, T.J.; Buetefisch, K.A.

    1998-01-01

    The technical codes for radiological monitoring of the waste air released from a radwaste repository demand that sampling for determination of aerosol-borne radioactivity is to be made with a screener equipped with a suitable number of measuring probes extending over the entire cross-sectional surface of the vent. Another requirement is to ensure that the waste air stream passing through the measuring channel is representative, containing the typical, operation-induced distribution of aerosols across the surface to be scanned. The study reported was intended to determine in a scaled-down model (1:10) of a repository ventilating duct the typical spatial distribution of aerosols (3D particulate density) in order to establish information on the type of typical distributions of aerosols, to be used for optimisation of the measuring site and monitoring instruments. (orig./CB) [de

  18. Radioactivity measurements in the vicinity of the mine waste heap at Crossen and radiation dose assessment

    Kulzer, R.

    1998-01-01

    The radiation dose to the population living in the vicinity of the mine waste heap is assessed. The measurements carried out were to verify the dose relevance of ambient radioactivity on site, in particular the ingestion and inhalation pathways and the external exposure pathways. The nuclide Pb-210 was used as an indicator because of its large dose factor for assessment of ingestion and its airborne dispersion as an Rn-222 daughter product. The waste heap material releases large quantities of this nuclide. Ingestion of radioactivity from the waste heap may be caused by wind-borne erosion and activity deposition on plants in the area. Therefore, the specific activities of Pb-210 and Ra-226 have been measured in soil and plant specimens sampled at various distances from the waste heap. (orig./CB) [de

  19. The treatment and conditioning of solid radioactive waste (1962)

    Cerre, P.; Mestre, E.

    1962-01-01

    Previous studies, the results of which have been confirmed by experiments, have led us to build a semi-industrial plant for the treatment and coating of solid radioactive waste. This report details the means at our disposal in a pilot plant which, apart from being used for tests, was also routine-operated. It is thus possible to give also an appreciation of its operation in this report. (authors) [fr

  20. High-level waste processing and conditioning: vitrification

    Bonniaud, R.

    1981-02-01

    The vitrification process used to treat fission product solutions at the Marcoule Vitrification Plant is described. The type of waste processed is characterized by its very high activity and the long lifetimes of some of the emitters that it contains. The performance obtained with this process is given together with the future developments envisaged. The storage of glasses is described as well as their behavior with time [fr

  1. Behavior of radioactive metal surrogates under various waste combustion conditions

    Yang, Hee Chul; Lee, Jae Hee; Kim, Jung Guk; Yoo, Jae Hyung; Kim, Joon Hyung

    2002-01-01

    A laboratory investigation of the behavior of radioactive metals under the various waste combustion atmospheres was conducted to predict the parameters that influence their partitioning behavior during waste incineration. Neodymium, samarium, cerium, gadolinium, cesium and cobalt were used as non-radioactive surrogate metals that are representative of uranium, plutonium, americium, curium, radioactive cesium, and radioactive cobalt, respectively. Except for cesium, all of the investigated surrogate metal compounds converted into each of their stable oxides at medium temperatures from 400 to 900 .deg. C, under oxygen-deficient and oxygen-sufficient atmospheres (0.001-atm and 0.21-atm O 2 ). At high temperatures above 1,400 .deg. C, cerium, neodymium and samarium in the form of their oxides started to vaporize but the vaporization rates were very slow up to 1500 .deg. C. Inorganic chlorine (NaCl) as well as organic chlorine (PVC) did not impact the volatility of investigated Nd 2 O 3 , CoO and Cs 2 O. The results of laboratory investigations suggested that the combustion chamber operating parameters affecting the entrainment of particulate and filtration equipment operating parameters affecting particle collection efficiency be the governing parameters of alpha radionuclides partitioning during waste incineration

  2. Sol - gel inorganic ion exchangers for conditioning of medium level radioactive waste

    Arcangeli, G.; Traverso, D.M.; Gerontopoulos, P.; Fava, R.

    1988-01-01

    Decontamination of high-level liquid wastes and medium activity wastes streams by inorganic ion exchange combined with the conversion of the spent inorganic ion exchange material to waste ceramics presents a considerable potential for utilisation in waste conditioning. Ceramic waste forms are found superior to other candidate waste immobilisation forms but practical implementation is hampered because of the complexity of the related fabrication technology. This report shows the possibility of improving this situation by resorting to sol gel techniques earlier developed for preparation of nuclear fuel ceramics. The principal findings are: - superior quality ion exchange xerogel titanates in the form of mechanically resistant, size controlled microspheres can be prepared using a simple sol-gel technique; - the titanate particles can be also used as precursors in Evaporative Deposition on Xerogel Particles (EDXP) a new waste solidification process based on physical impregnation of the xerogel material with the waste liquid followed by evaporation; - waste loaded ion exchange microspheres can be converted to leach resistant ceramics by firing and/or cold pressing and sintering at 900 0 -1100 0 C; - sol-gel inorganic ion exchange and EDXP may find useful application in conditioning MAW streams. 44 figs., 43 refs

  3. The role of waste package specifications as a forerunner to ILW repository conditions for acceptance

    Barlow, S.V.; Palmer, J.D.

    1998-01-01

    In the absence of a finalized repository site, design or associated safety case, Nirex is not in a position to issue conditions for acceptance. Nirex has therefore developed a strategy which facilitates packaging of intermediate level waste by providing guidance through waste package specifications, supported by the formal assessment of specific packaging proposals on a case-by-case basis. The waste package specifications are comprehensive and cover all aspects of the waste package including dimensions and other key features, performance standards, wasteform, quality assurance, and data recording requirements. The waste package specifications will be subject to periodic review as repository design and safety cases are finalized and will progressively become site- and design-specific. The waste package specifications will eventually form the basis for conditions for acceptance. The strategy described in this paper has been successfully followed by Nirex and customers for the past ten years and has permitted wastes to be packaged for a deep repository with confidence in the absence of a finalized site and safety cases for the repository. Because the process has its basis in a generic repository concept, it remains robust, despite the increased uncertainty following the March 1997 Secretary of State's decision, as to the siting and time-scale of a deep waste repository, and continues to be an important component of the UK's waste management strategy. (author)

  4. Development of thermal conditioning technology for Alpha-containment wastes: Alpha-contaminated waste incineration technology

    Kim, Joon Hyung; Kim, Jeong Guk; Yang, Hee Chul; Choi, Byung Seon; Jeong, Myeong Soo

    1999-03-01

    As the first step of a 3-year project named 'development of alpha-contaminated waste incineration technology', the basic information and data were reviewed, while focusing on establishment of R and D direction to develop the final goal, self-supporting treatment of α- wastes that would be generated from domestic nuclear industries. The status on α waste incineration technology of advanced states was reviewed. A conceptual design for α waste incineration process was suggested. Besides, removal characteristics of volatile metals and radionuclides in a low-temperature dry off-gas system were investigated. Radiation dose assessments and some modification for the Demonstration-scale Incineration Plant (DSIP) at Korea Atomic Energy Research Institute (KAERI) were also done

  5. Final Rule: 2013 Conditional Exclusions From Solid Waste and Hazardous Waste for Solvent-Contaminated Wipes

    This is a regulation page for the final rule EPA issued on July 31, 2013 that modifies the hazardous waste management regulations for solvent-contaminated wipes under the Resource Conservation and Recovery Act (RCRA).

  6. Development of thermal conditioning technology for Alpha-containment wastes: Alpha-contaminated waste incineration technology

    Kim, Joon Hyung; Kim, Jeong Guk; Yang, Hee Chul; Choi, Byung Seon; Jeong, Myeong Soo

    1999-03-01

    As the first step of a 3-year project named 'development of alpha-contaminated waste incineration technology', the basic information and data were reviewed, while focusing on establishment of R and D direction to develop the final goal, self-supporting treatment of {alpha}- wastes that would be generated from domestic nuclear industries. The status on {alpha} waste incineration technology of advanced states was reviewed. A conceptual design for {alpha} waste incineration process was suggested. Besides, removal characteristics of volatile metals and radionuclides in a low-temperature dry off-gas system were investigated. Radiation dose assessments and some modification for the Demonstration-scale Incineration Plant (DSIP) at Korea Atomic Energy Research Institute (KAERI) were also done.

  7. Materials interactions test methods to measure radionuclide release from waste forms under repository-relevant conditions

    Strickert, R.G.; Erikson, R.L.; Shade, J.W.

    1984-10-01

    At the request of the Basalt Waste Isolation Project, the Materials Characterization Center has collected and developed a set of procedures into a waste form compliance test method (MCC-14.4). The purpose of the test is to measure the steady-state concentrations of specified radionuclides in solutions contacting a waste form material. The test method uses a crushed waste form and basalt material suspended in a synthetic basalt groundwater and agitated for up to three months at 150 0 C under anoxic conditions. Elemental and radioisotopic analyses are made on filtered and unfiltered aliquots of the solution. Replicate experiments are performed and simultaneous tests are conducted with an approved test material (ATM) to help ensure precise and reliable data for the actual waste form material. Various features of the test method, equipment, and test conditions are reviewed. Experimental testing using actinide-doped borosilicate glasses are also discussed. 9 references, 2 tables

  8. Technical Performance Capability of Fourier Transform Profilometry for Quantitative Waste Volume Determination under Hanford Waste Tank Condition

    Monts, D.L.; Jang, P.R.; Long, Z.; Norton, O.P.; Okhuysen, W.P.; Su, Y.; Waggoner, Ch.A.

    2009-01-01

    The Hanford Site is currently in the process of an extensive effort to empty and close its radioactive single-shell and double-shell waste storage tanks. Before this can be accomplished, it is necessary to know how much residual material is left in a given waste tank and the chemical makeup of the residue. The Institute for Clean Energy Technology (ICET) at Mississippi State University is currently developing a quantitative in-tank inspection system based on Fourier Transform Profilometry (FTP). FTP is a non-contact, 3-D shape measurement technique. By projecting a fringe pattern onto a target surface and observing its deformation due to surface irregularities from a different view angle, FTP is capable of determining the height (depth) distribution (and hence volume distribution) of the target surface, thus reproducing the profile of the target accurately under a wide variety of conditions. Hence FTP has the potential to be utilized for quantitative determination of residual wastes within Hanford waste tanks. We report the results of a technical feasibility study to document the accuracy and precision of quantitative volume determination using the Fourier transform profilometry technique under simulated Hanford waste tank conditions. (authors)

  9. Radionuclide migration through porous cement-waste composition in semi-real conditions

    Plecas, I.; Peric, A.; Kostadinovic, A.

    1989-01-01

    In this paper, result of examination of Leakage rate or radionuclides Co-60 and Cs-137 in semi-real conditions are given. Radionuclides Co-60 and Cs-137 were immobilized by cement process and conditioned in concrete containers trying to make similar scenario for storing radioactive waste materials as in engineering trench system, repository. Experiments were realized with two waste water, evaporator bottom and reactor cooling system, (EB) and (RCS), from Nuclear Power Plants Krsko, in which the main radionuclides are Co-60 and Cs-137. These results will be used for future Yugoslav radioactive waste storing center (author)

  10. Obtaining and characterizing waste from red ceramics submitted to different conditions of burning

    Gomes, N.L.; Nascimento, R.L.P do; Ferreira, H.S.; Macedo, D.A. de; Dutra, R.P.S.

    2014-01-01

    One of the present industrial wastes generated in large quantities is the residue from the burning of the clay industry products, whether for breach of these products or are outside the technical specification. In this paper an analysis of the waste products produced in the laboratory under different thermal processing conditions, with varying firing temperatures of 500, 700, 900 and 1100 ° C was performed. The residues were characterized by X-ray fluorescence, X-ray diffraction and thermal analysis. The results show that the firing conditions influence the generated phases and thermal behavior of waste, which must have specific applications for their use. (author)

  11. Technical performance characterization of fourier transform profilometry for quantitative waste volume determination under Hanford waste tank conditions - 16281

    Monts, David L.; Jang, Ping-Rey; Long, Zhiling; Norton, Olin P.; Gresham, Lawrence L.; Su, Yi; Lindner, Jeffrey S.

    2009-01-01

    The Hanford Site in western Washington state is currently in the process of an extensive effort to empty and close its radioactive single-shell and double-shell waste storage tanks. Before this can be accomplished, it is necessary to know how much residual material is left in a given waste tank and the chemical makeup of the residue. The Institute for Clean Energy Technology (ICET) at Mississippi State University is currently developing an quantitative in-tank inspection system based on Fourier Transform Profilometry, FTP. FTP is a non-contact, 3-D shape measurement technique. By projecting a fringe pattern onto a target surface and observing its deformation due to surface irregularities from a different view angle, FTP is capable of determining the height (depth) distribution (and hence volume distribution) of the target surface, thus reproducing the profile of the target accurately under a wide variety of conditions. Hence FTP has the potential to be utilized for quantitative determination of residual wastes within Hanford waste tanks. We report the results of a technical feasibility study to document the accuracy and precision of quantitative volume determination using the Fourier transform profilometry technique under simulated Hanford waste tank conditions. We have initiated a technical feasibility assessment of the Fourier transform profilometry (FTP) technique for determining the volume of residual waste in Hanford radioactive waste tanks; preliminary results to date are presented in this paper. We find that we achieve FTP volume determinations with relatively small errors under conditions corresponding to the most challenging within a Hanford waste tank-viewing non-descript targets at a distance of 16.1 m (53 ft) and an angle of 62 deg.. We have determined that we can minimize measurement uncertainty by maximizing the camera-to-projector distance d, using an optical zoom of at least 5x, and ensuring that FTP images are only recorded after instrumental warm

  12. Developing technologies for conditioning the liquid organic radioactive wastes from Cernavoda NPP

    Deneanu, N.; Popescu, I. V.; Teoreanu, I.

    2004-01-01

    The Institute for Nuclear Research (INR)-Pitesti has developed technologies for conditioning liquid organic radioactive wastes (oils, miscellaneous solvent and liquid scintillation cocktail) for Cernavoda NPP. This paper describes the new and viable solidification technology to convert liquid organic radioactive wastes into a stable monolithic form, which minimizes the probability to release tritium in the environment during interim storage, transportation and final disposal. These are normally LLW containing only relatively small quantities of beta/gamma emitting radionuclides and variable amounts of tritium with activity below E+08Bq/l. The INR research staff in the radwaste area developed treatment/conditioning techniques and also designed and tested the containers for the final disposal, following the approach in the management of radwaste related to the nuclear fuel cycle. Thus, the INR focused this type of activity on treating and conditioning the wastes generated at Cernavoda Nuclear Power Plant consisting of lubricants from primary fuelling machines and turbine, the miscellaneous solvent from decontamination operation and the liquid scintillation cocktail used in radiochemical analysis. Laboratory studies on cementation of liquid organic radioactive wastes have been undertaken at INR Pitesti. One simple system, similar to a conventional cement solidification unit, can treat radioactive liquid wastes, which are the major components of low- and medium-level radioactive wastes generated by a Nuclear Power Plant. It was proved that the solidified waste could meet the Waste Acceptance Criteria of the disposal site, in this case Baita-Bihor National Repository, as follows: - The wastes are deposited in type A packages; - The maximum expected quantities of this waste stream that will be produced in the future are 50 drums per year. The maximum specific tritium activity per drum is 10 9 Bq/m 3 ; - Compressive strengths of the samples should be greater than 50 MPa

  13. Leaching of radioactive waste forms under saturated and unsaturated flow conditions

    Petelka, M.F.

    1987-01-01

    To predict the environmental impact of shallow land burial sites for radioactive waste, the mobilization and migration of waste nuclides must be estimated. The theoretical understanding that in potential leaching mechanisms leach-rate variations may arise from changes in both moisture content and volumetric flow rate was tested in column flow leach experiments using labeled vermiculite particles as a simulated waste form. As far as possible, conditions of flow rate and solution ion concentration were chosen to roughly approximate expected field conditions. A modified pressure-plate apparatus was developed, tested, and found suitable for the production of steady-state unsaturated conditions with leachate flow. Water content was determined using the gamma-ray attenuation method. The effects of several parameters on leaching were studied, including moisture content and pore velocity. Pore velocity effects were found to be negligible. It was found that the leach rate depends on the fraction of the exposed waste surface that is wetted and varies with the mobile water content in a non-linear fashion. The experimental results indicate that the release rate of radionuclides placed within a properly sited low-level waste disposal site may be two to three times smaller than that predicted assuming saturated conditions. This study was performed using a homogeneous fine-grained synthetic waste form, at room temperature, with a near neutral pH leachant and oxidizing conditions

  14. Recovery of Organic and Amino Acids from Sludge and Fish Waste in Sub Critical Water Conditions

    Muhammad Faisal

    2011-12-01

    Full Text Available The possibility of organic and amino acid production from the treatment of sludge and fish waste using water at sub critical conditions was investigated. The results indicated that at sub-critical conditions, where the ion product of water went through a maximum, the formation of organic acids was favorable. The presence of oxidant favored formation of acetic and formic acid. Other organic acids of significant amount were propionic, succinic and lactic acids. Depending on the type of wastes, formation of other organic acids was also possible. Knowing the organic acids obtained by hydrolysis and oxidation in sub-critical water of various wastes are useful in designing of applicable waste treatment process, complete degradation of organic wastes into volatile carbon and water, and also on the viewpoint of resource recovery. The production of lactic acid was discussed as well. The results indicated that temperature of 573 K, with the absence of oxidant, yield of lactic acid from fish waste was higher than sewage sludge. The maximum yield of total amino acids (137 mg/g-dry fish from waste fish entrails was obtained at subcritical condition (T = 523 K, P = 4 MPa at reaction time of 60 min by using the batch reactor. The amino acids obtained in this study were mainly alanine and glycine. Keywords:  organic acids, amino acids, sub-critical water, hydrothermal, resources recovery

  15. Performance of high level waste forms and engineered barriers under repository conditions

    1991-02-01

    The IAEA initiated in 1977 a co-ordinated research programme on the ''Evaluation of Solidified High-Level Waste Forms'' which was terminated in 1983. As there was a continuing need for international collaboration in research on solidified high-level waste form and spent fuel, the IAEA initiated a new programme in 1984. The new programme, besides including spent fuel and SYNROC, also placed greater emphasis on the effect of the engineered barriers of future repositories on the properties of the waste form. These engineered barriers included containers, overpacks, buffer and backfill materials etc. as components of the ''near-field'' of the repository. The Co-ordinated Research Programme on the Performance of High-Level Waste Forms and Engineered Barriers Under Repository Conditions had the objectives of promoting the exchange of information on the experience gained by different Member States in experimental performance data and technical model evaluation of solidified high level waste forms, components of the waste package and the complete waste management system under conditions relevant to final repository disposal. The programme includes studies on both irradiated spent fuel and glass and ceramic forms as the final solidified waste forms. The following topics were discussed: Leaching of vitrified high-level wastes, modelling of glass behaviour in clay, salt and granite repositories, environmental impacts of radionuclide release, synroc use for high--level waste solidification, leachate-rock interactions, spent fuel disposal in deep geologic repositories and radionuclide release mechanisms from various fuel types, radiolysis and selective leaching correlated with matrix alteration. Refs, figs and tabs

  16. Leach testing of waste glasses under near-saturation conditions

    Strachan, D.M.; Grambow, B.

    1983-11-01

    Two waste glasses, MCC 76 to 68 and C31 to 3, were leached in deionized water and 0.001 M MgCl 2 for periods up to 158 days. At 57 days the gel layer was removed from some of the specimens and leaching continued for up to 100 days. Results from leaching in deionized water showed that the gel layer was not protective. Results from leaching in 0.001 M MgCl 2 are in good agreement with the predicted results obtained from the use of the PHREEQE geochemical code and with sepiolite [Mg 2 Si 3 O 6 (OH) 4 ] as the Mg-bearing precipitate. Both B and Si were predicted and observed to increase with increasing glass dissolution while maintaining sepiolite solubility. Both MCC 76 to 68 and C31 to 3 glasses showed increased leaching in 0.001 M MgCl 2 upon removal of the layer. This suggests a leaching mechanism whereby leaching is driven by the formation of an alteration product

  17. Leaching behavior of a simulated bituminized radioactive waste form under deep geological conditions

    Nakayama, Shinichi; Iida, Yoshihisa; Nagano, Tetsushi; Akimoto, Toshiyuki

    2003-01-01

    The leaching behavior of a simulated bituminized waste form was studied to acquire data for the performance assessment of the geologic disposal of bituminized radioactive waste. Laboratory-scale leaching tests were performed for radioactive and non-radioactive waste specimens simulating bituminized waste of a French reprocessing company, COGEMA. The simulated waste was contacted with deionized water, an alkaline solution (0.03-mol/l KOH), and a saline solution (0.5-mol/l KCl) under atmospheric and anoxic conditions. The concentrations of Na, Ba, Cs, Sr, Np, Pu, NO 3 , SO 4 and I in the leachates were determined. Swelling of the bituminized waste progressed in deionized water and KOH. The release of the soluble components, Na and Cs, was enhanced by the swelling, and considered to be diffusion-controlled in the swelled layers of the specimens. The release of sparingly soluble components such as Ba and Np was solubility-limited in addition to the progression of leaching. Neptunium, a redox-sensitive element, showed a distinct difference in release between anoxic and atmospheric conditions. The elemental release from the bituminized waste specimens leached in the KCl was very low, which is likely due to the suppression of swelling of the specimens at high ionic strength. (author)

  18. Using Magnetically Responsive Tea Waste to Remove Lead in Waters under Environmentally Relevant Conditions

    Yeo, Siang Yee; Choi, Siwon; Dien, Vivian; Sow-Peh, Yoke Keow; Qi, Genggeng; Hatton, T. Alan; Doyle, Patrick S.; Thio, Beng Joo Reginald

    2013-01-01

    We report the use of a simple yet highly effective magnetite-waste tea composite to remove lead(II) (Pb2+) ions from water. Magnetite-waste tea composites were dispersed in four different types of water–deionized (DI), artificial rainwater, artificial groundwater and artificial freshwater–that mimic actual environmental conditions. The water samples had varying initial concentrations (0.16–5.55 ppm) of Pb2+ ions and were mixed with the magnetite-waste tea composite for at least 24 hours to allow adsorption of the Pb2+ ions to reach equilibrium. The magnetite-waste tea composites were stable in all the water samples for at least 3 months and could be easily removed from the aqueous media via the use of permanent magnets. We detected no significant leaching of iron (Fe) ions into the water from the magnetite-waste tea composites. The percentage of Pb adsorbed onto the magnetite-waste tea composite ranged from ~70% to 100%; the composites were as effective as activated carbon (AC) in removing the Pb2+ ions from water, depending on the initial Pb concentration. Our prepared magnetite-waste tea composites show promise as a green, inexpensive and highly effective sorbent for removal of Pb in water under environmentally realistic conditions.

  19. Using Magnetically Responsive Tea Waste to Remove Lead in Waters under Environmentally Relevant Conditions

    Yeo, Siang Yee

    2013-06-20

    We report the use of a simple yet highly effective magnetite-waste tea composite to remove lead(II) (Pb2+) ions from water. Magnetite-waste tea composites were dispersed in four different types of water–deionized (DI), artificial rainwater, artificial groundwater and artificial freshwater–that mimic actual environmental conditions. The water samples had varying initial concentrations (0.16–5.55 ppm) of Pb2+ ions and were mixed with the magnetite-waste tea composite for at least 24 hours to allow adsorption of the Pb2+ ions to reach equilibrium. The magnetite-waste tea composites were stable in all the water samples for at least 3 months and could be easily removed from the aqueous media via the use of permanent magnets. We detected no significant leaching of iron (Fe) ions into the water from the magnetite-waste tea composites. The percentage of Pb adsorbed onto the magnetite-waste tea composite ranged from ~70% to 100%; the composites were as effective as activated carbon (AC) in removing the Pb2+ ions from water, depending on the initial Pb concentration. Our prepared magnetite-waste tea composites show promise as a green, inexpensive and highly effective sorbent for removal of Pb in water under environmentally realistic conditions.

  20. Assessment of biogas production from MBT waste under different operating conditions

    Pantini, Sara; Verginelli, Jason; Lombardi, Francesco

    2015-01-01

    In this work, the influence of different operating conditions on the biogas production from mechanically-. biologically treated (MBT) wastes is investigated. Specifically, different lab-scale anaerobic tests varying the water content (26-43% w/w up to 75% w/w), the temperature (from 20 to 25......, the obtained results highlighted that the operative conditions can drastically affect the gas production from MET wastes. This suggests that particular caution should be paid when using the results of lab-scale tests for the evaluation of long-term behaviour expected in the field where the boundary conditions...

  1. Effect of storage conditions on the calorific value of municipal solid waste.

    Nzioka, Antony Mutua; Hwang, Hyeon-Uk; Kim, Myung-Gyun; Yan, Cao Zheng; Lee, Chang-Soo; Kim, Young-Ju

    2017-08-01

    Storage conditions are considered to be an important factor as far as waste material characteristics are concerned. This experimental investigation was conducted using municipal solid waste (MSW) with a high moisture content and varying composition of organic waste. The objective of this study was to understand the effect of storage conditions and temperature on the moisture content and calorific value of the waste. Samples were subjected to two different storage conditions and investigated at specified temperatures. The composition of sample materials investigated was varied for each storage condition and temperature respectively. Gross calorific value was determined experimentally while net calorific value was calculated using empirical formulas proposed by other researchers. Results showed minimal changes in moisture content as well as in gross and net calorific values when the samples were subjected to sealed storage conditions. Moisture content reduced due to the ventilation process and the rate of moisture removal increased with a rise in storage temperature. As expected, rate of moisture removal had a positive effect on gross and net calorific values. Net calorific values also increased at varying rates with a simultaneous decrease in moisture content. Experimental investigation showed the effectiveness of ventilation in improving the combustion characteristics of the waste.

  2. Detoxification of wood preserving waste under ambient, enhanced and chemical pretreatment conditions

    Hong, M.S.; Brown, K.W.; Dale, B.E.; Donnelly, K.C.; He, L.Y.; Markiewicz, K.V. [Texas A and M Univ., College Station, TX (United States)

    1994-12-31

    Detoxification of pentachlorophenol-containing wood preserving waste was monitored under ambient, enhanced and chemical pretreatment conditions for genotoxicity and parent compound removal. Samples were collected throughout the treatment periods and sequentially extracted with dichloromethane and methanol with the Tecator Soxtec apparatus. The organic extracts were analyzed on GC/ECD and GC/MS. The extract mutagenic and genotoxic potentials were evaluated with and without metabolic activation with the Salmonella Microsomal and E. coli Prophage Induction assays. The Salmonella mutagenic responses of extracts from Weswood soil amended with wood preserving waste and treated under ambient conditions were 2.0, 34.6 and 2.4 times greater than the solvent control on days 0, 540 and 1,200 respectively. Organic extracts of soil amended with wood preserving waste and treated under enhanced conditions in a solid-phase rotating drum bioreactor had mutagenic potentials of 3.4, 4.9 and 3.5 on days 0, 14 and 30, respectively. Extracts from wood preserving waste sludge treated with potassium polyethylene glycol were shown to have mutagenic potentials of 2.8, 6.1 and 3.8 at 0, 10 and 30 minutes. The results indicate that the initial products of the wood preserving waste detoxification under all treatment conditions appear to have greater genotoxic potentials than the starting material. The results also suggest that a more rapid detoxification occurs under enhanced and chemical pretreatment conditions.

  3. Co-conditioning and dewatering of chemical sludge and waste activated sludge.

    Chang, G R; Liu, J C; Lee, D J

    2001-03-01

    The conditioning and dewatering behaviors of chemical and waste activated sludges from a tannery were studied. Capillary suction time (CST), specific resistance to filtration (SRF), and bound water content were used to evaluate the sludge dewatering behaviors. Zeta potentials were also measured. Experiments were conducted on each sludge conditioned and dewatered separately, and on the sludge mixed at various ratios. Results indicate that the chemical sludge was relatively difficult to be dewatered, even in the presence of polyelectrolyte. When the waste activated sludge was mixed with the chemical sludge at ratios of 1:1 and 2:1, respectively, the dewaterability of chemical sludge improved remarkably while the relatively better dewaterability of the waste activated sludge deteriorated only to a limited extent. As the mixing ratios became 4:1 and 8:1, the dewaterability of the mixed sludge was equal to that of the waste activated sludge. The optimal polyelectrolyte dosage for the mixed sludge was equal to or less than that of the waste activated sludge. It is proposed that the chemical sludges act as skeleton builders that reduce the compressibility of the mixed sludge whose dewaterability is enhanced. Bound water contents of sludge decreased at low polyelectrolyte dosage and were not significantly affected as polyelectrolyte dosage increased. Advantages and disadvantages of co-conditioning and dewatering chemical sludge and waste activated sludge were discussed.

  4. Boro Silicate Glass: The proven Conditioning of RTR ultimate Waste

    Bartagnon, O.; Petitjean, V.

    2002-01-01

    The possibility to dispose of the RTR spent fuel in a geological repository is neither internationally foreseen nor seems realistic. This due to degradation phenomena and possible criticality incidents. The conditioning by reprocessing is the only solution for back end management of TRT spent fuels

  5. Corrosion of carbon steel under waste disposal conditions

    Marsh, G.

    1990-01-01

    The corrosion of carbon steel has been studied in the United Kingdom under granitic groundwater conditions, with pH between 5 and 10 and possibly substantial amounts of Cl - , SO 4 2- and HCO 3 - /CO 3 2- . Corrosion modes considered include uniform corrosion under both aerobic and anaerobic conditions; passive corrosion; localized attack in the form of pitting or crevice corrosion; and environmentally assisted cracking - hydrogen embrittlement or stress corrosion cracking. Studies of these processes are being carried out in order to predict the metal thicknesses required to give container lifetimes of 500 to 1000 years. A simple uniform corrosion model predicts a corrosion rate of around 13.4 μm/a at 20C, rising to 69 μm/a at 50C and 208 μm/a at 90C. A radiation dose of 10 5 rad/h and a G-value of 2.8 for the production of oxidizing species would account for an increase in corrosion rate of 7 μm/a. This model overestimates slightly the results actually achieved for experimental samples exposed for two years, the difference being due to a protective film formed on the samples. These corrosion rates predict that the container must be 227 mm thick to withstand uniform corrosion; however, they predict very high levels of hydrogen production. Conditions will be favourable for localized or pitting corrosion for about 125 years, leading to a maximum penetration of 160 mm. Since the exposure environment cannot be predicted precisely, one cannot state that stress corrosion cracking is impossible. Thus the container must be stress relieved. Other corrosion mechanisms such as microbial corrosion and hydrogen embrittlement are not considered significant

  6. Treatment of Household Waste in Small Towns of China: Status, Basic Conditions and Appropriate Modes

    HE Pin-jing

    2015-04-01

    Full Text Available Small town is the gateway of population migrating from rural areas to urban areas in the process of urbanization. The level of its household solid waste treatment is pivotal to the environmental and sanitary quality of surrounding rural areas. Furthermore, small town is the primary administrative center for rural districts, and will impose important influences on the solid waste management in villages. Therefore, it is necessary to investigate the effects of treatment modes on the household solid waste treatment in towns and surrounding villages. Based on the waste generation in small towns, this study analyzed the current status and existing problems for solid waste treatment, and discussed the related administrative management and financial supporting conditions in small towns. By summarizing the characteristics of the existing modes and comparing the costs for different treatment modes, the present study proposed that the most appropriate mode was“diversion in villages-diversion, transportation or treatment in towns-treatment and disposal in counties”, in which the town was the core node for the treatment of rural solid waste, so that the administrative and financial advantages of small towns could be highlighted and consequentially promoted the management of rural solid waste.

  7. Experience and Lessons Learned from Conditioning of Spent Sealed Sources in Singapore - 13107

    Hong, Dae-Seok; Kang, Il-Sik; Jang, Kyung-Duk; Jang, Won-Hyuk [Korea Atomic Energy Research Institute, 1045 Daedeokdaero, Yuseong, Daejeon (Korea, Republic of); Hoo, Wee-Teck [National Environment Agency, 40 Scotts Road 228231 (Singapore)

    2013-07-01

    In 2010, IAEA requested KAERI (Korea Atomic Energy Research Institute) to support Singapore for conditioning spent sealed sources. Those that had been used for a lightning conductor, check source, or smoke detector, various sealed sources had been collected and stored by the NEA (National Environment Agency) in Singapore. Based on experiences for the conditioning of Ra-226 sources in some Asian countries since 2000, KAERI sent an expert team to Singapore for the safe management of spent sealed sources in 2011. As a result of the conditioning, about 575.21 mCi of Am-241, Ra-226, Co-60, and Sr-90 were safely conditioned in 3 concrete lining drums with the cooperation of the KAERI expert team, the IAEA supervisor, the NEA staff and local laborers in Singapore. Some lessons were learned during the operation: (1) preparations by a local authority are very helpful for an efficient operation, (2) a preliminary inspection by an expert team is helpful for the operation, (3) brief reports before and after daily operation are useful for communication, and (4) a training opportunity is required for the sustainability of the expert team. (authors)

  8. Development of methods for treatment and conditioning of biological radioactive waste in the Czech Republic

    Holub, J [NYCOM, Prague (Czech Republic)

    1997-02-01

    Incineration of biological radioactive waste was performed in a facility manufactured in the Czech Republic for combustion of burnable, radioactive and non-radioactive residues. The equipment has shown an adequate capability for combustion of biological waste. Basic technical parameters of the incinerator SP-603 can guarantee combustion of majority of wastes from different radionuclide users in the country. To ensure proper further handling with the resulting ash, three conditioning options were studied, the bituminization process, incorporation into cement, and embedding of ash into a mixture of bituminous and cementitious materials. Mechanical properties of the conditioned ash were in good compliance with those published elsewhere. Bituminized ash exhibits lowest leachibility, followed by the ash conditioned by means of the mixed process. Potential abnormal operation conditions were evaluated and their consequences assessed. The evaluation encompassed sensitivity analysis of the consequences potentially affecting the operating staff, nearby population and the environment. Cost estimate was carried out using a national approach for the calculation. From the results it can be seen that there are no large differences between the conditioning and disposal of wastes resulting from different conditioning processes. (author). 16 refs, 4 figs, 15 tabs.

  9. Development of methods for treatment and conditioning of biological radioactive waste in the Czech Republic

    Holub, J.

    1997-01-01

    Incineration of biological radioactive waste was performed in a facility manufactured in the Czech Republic for combustion of burnable, radioactive and non-radioactive residues. The equipment has shown an adequate capability for combustion of biological waste. Basic technical parameters of the incinerator SP-603 can guarantee combustion of majority of wastes from different radionuclide users in the country. To ensure proper further handling with the resulting ash, three conditioning options were studied, the bituminization process, incorporation into cement, and embedding of ash into a mixture of bituminous and cementitious materials. Mechanical properties of the conditioned ash were in good compliance with those published elsewhere. Bituminized ash exhibits lowest leachibility, followed by the ash conditioned by means of the mixed process. Potential abnormal operation conditions were evaluated and their consequences assessed. The evaluation encompassed sensitivity analysis of the consequences potentially affecting the operating staff, nearby population and the environment. Cost estimate was carried out using a national approach for the calculation. From the results it can be seen that there are no large differences between the conditioning and disposal of wastes resulting from different conditioning processes. (author). 16 refs, 4 figs, 15 tabs

  10. Development of integrated radioactive waste packaging and conditioning solutions in the UK

    Sibley, Peter; Butter, Kevin; Zimmerman, Ian [EnergySolutions EU Ltd., Swindon, Wiltshire (United Kingdom); Viermann, Joerg [GNS Gesellschaft fur Nuklear-Service mbH, Essen (Germany); Messer, Matthias [GNS Gesellschaft fur Nuklear-Service mbH, Bristol (United Kingdom)

    2013-07-01

    In order to offer a more cost effective, safer and efficient Intermediate Level Waste (ILW) management service, EnergySolutions EU Ltd. and Gesellschaft fur Nuklear-Service mbH (GNS) have been engaged in the development of integrated radioactive waste retrieval, packaging and conditioning solutions in the UK. Recognising the challenges surrounding regulatory endorsement and on-site implementation in particular, this has resulted in an alternative approach to meeting customer, safety regulator and disposability requirements. By working closely with waste producers and the organisation(s) responsible for endorsing radioactive waste management operations in the UK, our proposed solutions are now being implemented. By combining GNS' off-the-shelf, proven Ductile Cast Iron Containers (DCICs) and water removal technologies, with EnergySolutions EU Ltd.'s experience and expertise in waste retrieval, safety case development and disposability submissions, a fully integrated service offering has been developed. This has involved significant effort to overcome technical challenges such as onsite equipment deployment, active commissioning, conditioning success criteria and disposability acceptance. Our experience in developing such integrated solutions has highlighted the importance of working in collaboration with all parties to achieve a successful and viable outcome. Ultimately, the goal is to ensure reliable, safe and effective delivery of waste management solutions. (authors)

  11. Systematic handling of requirements and conditions (in compliance with waste acceptance requirements for a radioactive waste disposal facility)

    Keyser, Peter; Helander, Anita

    2012-01-01

    This Abstract and presentation will demonstrate the need for a structured requirement management and draw upon experiences and development from SKB requirements data base and methodology, in addition to international guidelines and software tools. The presentation will include a discussion on how requirement management can be applied for the decommissioning area. The key issue in the decommissioning of nuclear facilities is the progressive removal of hazards, by stepwise decontamination and dismantling activities that have to be carried out safely and within the boundaries of an approved safety case. For decommissioning there exists at least two safety cases, one for the pre-disposal activities and one for the disposal facility, and a need for a systematic handling of requirements and conditions to safely manage the radioactive waste in the long term. The decommissioning safety case is a collection of arguments and evidence to demonstrate the safety of a decommissioning project. It also includes analyzing and updating the decommissioning safety case in accordance with the waste acceptance criteria's and the expected output, i.e. waste packages. It is a continuous process to confirm that all requirements have been met. On the other hand there is the safety case for a radioactive waste disposal facility, which may include the following processes and requirements: i) Integrating relevant scientific (and other) information in a structured, traceable and transparent way and, thereby, developing and demonstrating an understanding of the potential behavior and performance of the disposal system; ii) Identifying uncertainties in the behavior and performance of the disposal system, describing the possible significance of the uncertainties, and identifying approaches for the management of significant uncertainties; iii) Demonstrating long-term safety and providing reasonable assurance that the disposal facility will perform in a manner that protects human health and the

  12. A radioactive waste transportation package monitoring system for normal transport and accident emergency response conditions

    Brown, G.S.; Cashwell, J.W.; Apple, M.L.

    1993-01-01

    This paper addresses spent fuel and high level waste transportation history and prospects, discusses accident histories of radioactive material transport, discusses emergency responder needs and provides a general description of the Transportation Intelligent Monitoring System (TRANSIMS) design. The key objectives of the monitoring system are twofold: (1) to facilitate effective emergency response to accidents involving a radioactive waste transportation package, while minimizing risk to the public and emergency first-response personnel, and (2) to allow remote monitoring of transportation vehicle and payload conditions to enable research into radioactive material transportation for normal and accident conditions. (J.P.N.)

  13. New volume reduction conditioning options for solid alpha-bearing waste

    Jouan, A.; Jacquet-Francillon, N.; Kertesz, C.; Frotscher, H.; Ganser, B.; Klein, M.

    1990-01-01

    The current and future development of nuclear energy requires increasing allowance for nuclear waste treatment: α-bearing wastes destined for geological storage are already conditioned, generally in a cement matrix. Other containment processes producing higher quality matrices and allowing volume reduction have been investigated over the last five years by the General Directorate for Science Research and Development of the Commission of the European Communities. This paper discusses the work on conditioning α-bearing ashes produced by incineration of contaminated combustible materials, and on fuel cladding hulls resulting from spent fuel reprocessing

  14. Data base system for research and development of high-level waste conditioning

    Masaki, Toshio; Igarashi, Hiroshi; Ohuchi, Jin; Miyauchi, Tomoko.

    1992-01-01

    Results of research and development for High-Level Waste Conditioning are accumulated as large number of documents. Data Base System for Research and Development of High-Level Waste Conditioning has been developed since 1987 to search for necessary informations correctly and rapidly with the intention of offering and transferring the results to organization inside and outside of PNC. This data base system has contributed that technical informations has been correctly and rapidly searched. Designing of devices etc. and making of reports have become easy and work has been efficiently and rationally accomplished. (author)

  15. Decision for counting condition of radioactive waste activities measuring by Ludlum detector

    Bambang-Purwanto

    2000-01-01

    Radioactive waste must measured for activities before be throw out to environment. Measuring will be important in ordered to know activities can be given management direction. For activities radioactive waste on limit threshold value must processed, but for under limit threshold value activities can be throw out to environment. Activities measuring for solid radioactive waste and liquid by (Total, β, γ) Ludlum detector connected Mode-1000 Scaler Counting. Before measuring for solid waste activities was decisioned optimally counting condition, and be obtained are : sample weight 3.5 gram, heating temperature of 125 o C and heating time at 60 minutes. Activities measuring result by total detector ranges from (0.68-0.71) 10 -1 μCi/gram, β detector ranges from (0.24-0.25) 10 -1 μCi/gram and γ detector ranges from (0.35-0.37) μCi/gram

  16. Conditioning of high activity solid waste: fuel claddings and dissolution residues

    Anon.

    1982-01-01

    This chapter reports on experimental studies of embedding into matrix material, the melting and conversion of zircaloy, and waste properties and characterization. Methods are developed for embedding the waste scrap into a solid and resistant matrix material in order to confine the radioactivity and to prevent it from dispersion. The matrix materials investigated are lead alloys, ceramics and compacted graphite or aluminium powder. The treatment of fuel hulls by melting or chemical conversion is described. Cemented hulls are characterized and the pyrophoricity of zircaloy fines is investigated. Topics considered include the embedding of hulls into graphite and aluminium, the embedding of hulls and dissolution residues into alumino-ceramics, the solidification of alpha-bearing wastes into a ceramic matrix, and the conditioning of cladding waste by eutectoidic melting and by embedding in glass

  17. Design and operation of off-gas cleaning systems at high level liquid waste conditioning facilities

    1988-01-01

    The immobilization of high level liquid wastes from the reprocessing of irradiated nuclear fuels is of great interest and serious efforts are being undertaken to find a satisfactory technical solution. Volatilization of fission product elements during immobilization poses the potential for the release of radioactive substances to the environment and necessitates effective off-gas cleaning systems. This report describes typical off-gas cleaning systems used in the most advanced high level liquid waste immobilization plants and considers most of the equipment and components which can be used for the efficient retention of the aerosols and volatile contaminants. In the case of a nuclear facility consisting of several different facilities, release limits are generally prescribed for the nuclear facility as a whole. Since high level liquid waste conditioning (calcination, vitrification, etc.) facilities are usually located at fuel reprocessing sites (where the majority of the high level liquid wastes originates), the off-gas cleaning system should be designed so that the airborne radioactivity discharge of the whole site, including the emission of the waste conditioning facility, can be kept below the permitted limits. This report deals with the sources and composition of different kinds of high level liquid wastes and describes briefly the main high level liquid waste solidification processes examining the sources and characteristics of the off-gas contaminants to be retained by the off-gas cleaning system. The equipment and components of typical off-gas systems used in the most advanced (large pilot or industrial scale) high level liquid waste solidification plants are described. Safety considerations for the design and safe operation of the off-gas systems are discussed. 60 refs, 31 figs, 17 tabs

  18. Development of radioactive solid waste retrieving and conditioning technology in CIAE

    Li Meishan

    2005-01-01

    For the past 50 years, more than 40,000 m 3 LILW were generated during defense production and research in china. Most of the waste are still storing in pit-type storage facilities, which were designed by the former Soviet Russia in China. Up to now the project on solid waste retrieving and conditioning hasn't been carried out in China. At the beginning of the last century 90s 'R and D of retrieving, sorting, and compaction technologies of LILW' had been done in CIAE. In 2002, the authorities ratified the project about LILW retrieving from the pit-type storage facilities and conditioning by super-compaction. It is the first time to retrieve the solid waste from pit-type storage facilities in China. What's more, almost there are no similar projects in the world. The project consists of three parts: waste retrieving unit, waste pre-treating unit and conditioning unit, which is super-compaction workshop. It will set a good example for other similar facilities in the Nuclear Energy Industry after the project will have been completed successfully. (authors)

  19. Waste conditioning components for a new radwaste building

    Lewitz, J.C.; Stoelken, G.

    2001-01-01

    In the year 1999 Hansa Projekt Anlagentechnik GmbH made a basic study for the equipment of a new to be build radwaste building for TPC, Taiwan. Within an offer there was made an overall concept together with a proposal for system integration including supply, erection and put into operation for the following components supercompactor with in-/output device, overpack-filling station, resindrying- and filling unit, sorting tables for solid radwaste, cementation unit for liquid radwaste, cementation unit for grouting, drum inspection and decontamination station, storages for primary and conditioned radwaste, HVAC with filtration for several components and a roller conveyor system for transfer throughout the radwaste building. This overall concept was to be realized very similar by the client. The HPA scope of supply was focused onto the key components supercompactor with in-/output device, roller conveyor and turntable for cartridges and pellets, overpack-filling station, sorting tables, HVAC with filtration for supercompactor and sorting tables, and last but not least a drum inspection and decontamination system. In the following at first the functioning of HPA-components and the system as whole will be declared. At second components and system will be shown in detail together with figures and technical data. (orig.)

  20. Co-digestion of bovine slaughterhouse wastes, cow manure, various crops and municipal solid waste at thermophilic conditions: a comparison with specific case running at mesophilic conditions.

    Pagés-Díaz, J; Sárvári-Horváth, I; Pérez-Olmo, J; Pereda-Reyes, I

    2013-01-01

    A co-digestion process was evaluated when mixing different ratios of agro-industrial residues, i.e. bovine slaughterhouse waste (SB); cow manure (M); various crop residues (VC); and municipal solid waste (MSW) by anaerobic batch digestion under thermophilic conditions (55 °C). A selected study case at mesophilic condition (37 °C) was also investigated. The performance of the co-digestion was evaluated by kinetics (k(0)). The best kinetic results were obtained under thermophilic operation when a mixture of 22% w/w SB, 22% w/w M, 45% w/w VC and 11% w/w MSW was co-digested, which showed a proper combination of high values in r(s)CH(4) and k(0) (0.066 Nm(3)CH(4)/kgVS*d, 0.336 d(-1)) during the anaerobic process. The effect of temperature on methane yield (Y(CH4)), specific methane rate (r(s)CH(4)) and k(0) was also analyzed for a specific study case; there a mixture of 25% w/w of SB, 37.5% w/w of M, 37.5% of VC and 0% of MSW was used. Response variables were severely affected by mesophilic conditions, diminishing to at least 45% of the thermophilic values obtained for a similar mixture. The effect of temperature suggested that thermophilic conditions are suitable to treat these residues.

  1. Optimalization studies concerning volume reduction and conditioning of radioactive waste in view of storage and disposal (geological disposal into clay)

    Dejonghe, P.; Van De Voorde, N.; Bonne, A.

    1984-01-01

    Volume reduction of low-level and medium-level wastes, and simultaneous optimization of the quality of the conditioned end-product is a major challenge in the management of radioactive wastes. Comments will be given on recent achievements in treatment of non-high-level liquid and solid wastes from power reactors and low-level plutonium contaminated wastes. The latter results can contribute to an overall optimization of a radioactive waste management scheme, including the final disposal of the conditioned materials. Some detailed results will be given concerning volume reduction, decontamination factors, degree of immobilization of the contained radioelements, and cost considerations

  2. Studies on cement matrix materials used at the Radioactive Waste Treatment Plant for radwaste conditioning

    Dragolici, Felicia; Lungu, Laura; Nicu, Mihaela; Rotarescu, Gheorghe; Turcanu, Corneliu

    2003-01-01

    The research activities performed by Department of Radioactive Waste Management is focused on the treatment of LLAW products obtained by chemical precipitation and on the conditioning of these products by cementation. The individual mechanisms implied in the chemical precipitation processes are directly dependent on the precipitate properties and structure, which in turn are connected with the initial system composition and the precipitation procedure, i.e. reagent concentration, rate and orders of chemical addition, mixing rate and time and ageing conditions. In case of conditioning by cementation, the chemical nature and proportion of the sludges or concentrates affect both the hydrolysis of the initial cement components and the reactions of metastable hydration constituents, as well as the mechanical strength and chemical resistance of the hardened cemented matrix.Generally, the study of the precipitation products and their behaviour during cementation and the long-term disposal is extremely difficult because of the system complexity (phase composition and structure) and the lack of the non-destructive analytical methods. The experience accumulated by the countries who advanced nuclear programmes in military and socio-economic fields and which produced important volumes of radioactive wastes, leads us to study some of mineral additives to be used in the conditioning and disposal technology. Is well known that some mineral additives can diminish the leaching rate of the radionuclides in the disposal environment.The studies have the purpose to obtain the most propitious mixture of cement-bentonite and cement-volcanic tuff, which have the mechanical properties similar to the cement paste used for the conditioning of radioactive waste.Taking into account the characteristics of these mineral binders, namely a very good plasticity and capacity of adsorption, which lead at the decrease of porosity, the mixture is planned to be used in the future, at the Radioactive

  3. Conditioning and handling of tritiated wastes at Canadian nuclear power facilities

    Krochmalnek, L.S.; Krasznai, J.P.; Carney, M.

    1987-04-01

    Ontario Hydro operates a 10,000 MW capacity nuclear power system utilizing the CANDU pressurized heavy water reactor design. The use of D 2 O as moderator and coolant results in the production of about 2400 Ci of tritium per MWe-yr. As a result, there is significant Canadian experience in the treatment, handling, transport and storage of tritiated wastes. Ontario Hydro operates its own reactor waste storage site which includes systems for volume reduction, immobilization and packaging of wastes. In addition, a facility to remove tritium from heavy water is presently being commissioned at the Darlington nuclear site. This facility will generate tritiated liquid and solid waste that will have to be properly conditioned prior to storage or disposal. The nature of these various wastes and the processes/packaging required to meet storage/disposal criteria are judged to have relevance to investigations in fusion facility waste arisings. Experience to date, planned operational procedures and ongoing R and D in this area are described

  4. Information about activity, status and radiation conditions of Republic radioactive waste repository

    Saidumarov, P.

    2000-01-01

    All radioactive wastes in the Republic of Uzbekistan are stored in the Republic Radioactive Waste Repository in Parkent district of Tashkent region. In the facility there are 2 tanks for solid radioactive waste, each of 800 m 3 , one of them is full, second is in operation; 2 tanks for liquid radioactive waste each tank of 200 m 3 , both of them are empty; 6 storages, each of 3 m 3 all of them are empty; 3 storages for spent radioactive sources, one of them is full, 2 of them are in operation; 4 storages for high level radioactive waste, each storage of 3.5 m 3 , one of them is in operation, 3 are empty; one sealed storage containing 135 m 3 of concrete blocks with waste from electronic industry. According to conclusions of a few competent examinations RRWR does not cause damage to the environment. Geographic location and technical conditions of the repository are satisfactory. Low deposition of underground water (62 m) excludes penetration of radioisotopes. There were no radiation accidents during the repository operation

  5. Yeast production from cellulase hydrolyzed furfural industrial waste. II. Conditions for the cultivation of yeast

    1977-01-01

    Three yeast strains, Candida AS 2-121, C. utilis AS 2-1180, and C. tropicalis AS 2-637 were selected as being capable of growing on cellulase-hydrolyzed furfural industrial waste. Cell mass yields with respect to C source were approximately 50%. Fermentation conditions are given.

  6. Techniques of treatment or conditioning for waste arising from 131I production

    Dellamono, J.C.

    1989-07-01

    Distillation, evaporation/crystallization, direct immobilization and some chemical like precipitation and reduction were studied as techniques of treatment or conditioning for waste arising from 131 I production. The description of all techniques studied, as well as evaluation and discussion of the results are presented. (author) [pt

  7. Methodology applied in Cuba for siting, designing, and building a radioactive waste repository under safety conditions

    Orbera, L.; Peralta, J.L.; Franklin, R.; Gil, R.; Chales, G.; Rodriguez, A.

    1993-01-01

    The work presents the methodology used in Cuba for siting, designing, and building a radioactive waste repository safely. This methodology covers both the technical and socio-economic factors, as well as those of design and construction so as to have a safe siting for this kind of repository under Cuba especial condition. Applying this methodology will results in a safe repository

  8. Thermal processing of conditioned waste and fuel substitutes; Thermische Behandlung vorbehandelter Abfaelle und Ersatzbrennstoffe

    Velden, F. van der; Engweiler, J. [Von Roll Umwelttechnik AG, Zurich (Switzerland)

    1998-12-31

    Different technologies for the thermal processing of mechanical-biologically conditioned waste are described and compared in terms of cost and flexibility. (orig.) [Deutsch] Es werden verschiedene Technologien der thermischen Behandlung mechanisch-biologisch vorbehandelter Abfaelle vorgestellt und im Hinblick auf Kosten und Flexibilitaet verglichen. (orig.)

  9. Assessment of biogas production from MBT waste under different operating conditions

    Pantini, Sara, E-mail: pantini@ing.uniroma2.it [Department of Civil Engineering and Computer Science Engineering, University of Rome “Tor Vergata”, Via del Politecnico, 1, 00133 Rome (Italy); Verginelli, Iason; Lombardi, Francesco [Department of Civil Engineering and Computer Science Engineering, University of Rome “Tor Vergata”, Via del Politecnico, 1, 00133 Rome (Italy); Scheutz, Charlotte; Kjeldsen, Peter [Department of Environmental Engineering, Technical University of Denmark, Miljoevej, Building 113, DK-2800 Kgs. Lyngby (Denmark)

    2015-09-15

    Highlights: • BMP test displayed high gas potential generation capacity of MBT waste. • Strong inhibition effects were observed due to ammonia and VFA accumulation. • Waste water content was found as the key parameter limiting gas generation. • First order k-values were determined for different operating conditions. - Abstract: In this work, the influence of different operating conditions on the biogas production from mechanically–biologically treated (MBT) wastes is investigated. Specifically, different lab-scale anaerobic tests varying the water content (26–43% w/w up to 75% w/w), the temperature (from 20 to 25 °C up to 55 °C) and the amount of inoculum have been performed on waste samples collected from a full-scale Italian MBT plant. For each test, the gas generation yield and, where applicable, the first-order gas generation rates were determined. Nearly all tests were characterised by a quite long lag-phase. This result was mainly ascribed to the inhibition effects resulting from the high concentrations of volatile fatty acids (VFAs) and ammonia detected in the different stages of the experiments. Furthermore, water content was found as one of the key factor limiting the anaerobic biological process. Indeed, the experimental results showed that when the moisture was lower than 32% w/w, the methanogenic microbial activity was completely inhibited. For the higher water content tested (75% w/w), high values of accumulated gas volume (up to 150 Nl/kgTS) and a relatively short time period to deplete the MBT waste gas generation capacity were observed. At these test conditions, the effect of temperature became evident, leading to gas generation rates of 0.007 d{sup −1} at room temperature that increased to 0.03–0.05 d{sup −1} at 37 °C and to 0.04–0.11 d{sup −1} at 55 °C. Overall, the obtained results highlighted that the operative conditions can drastically affect the gas production from MBT wastes. This suggests that particular caution

  10. Modeling of hydrologic conditions and solute movement in processed oil shale waste embankments under simulated climatic conditions

    Reeves, T.L.; Turner, J.P.; Hasfurther, V.R.; Skinner, Q.D.

    1992-06-01

    The scope of this program is to study interacting hydrologic, geotechnical, and chemical factors affecting the behavior and disposal of combusted processed oil shale. The research combines bench-scale testing with large scale research sufficient to describe commercial scale embankment behavior. The large scale approach was accomplished by establishing five lysimeters, each 7.3 x 3.0 x 3.0 m deep, filled with processed oil shale that has been retorted and combusted by the Lurgi-Ruhrgas (Lurgi) process. Approximately 400 tons of Lurgi processed oil shale waste was provided by RBOSC to carry out this study. Research objectives were designed to evaluate hydrologic, geotechnical, and chemical properties and conditions which would affect the design and performance of large-scale embankments. The objectives of this research are: assess the unsaturated movement and redistribution of water and the development of potential saturated zones and drainage in disposed processed oil shale under natural and simulated climatic conditions; assess the unsaturated movement of solubles and major chemical constituents in disposed processed oil shale under natural and simulated climatic conditions; assess the physical and constitutive properties of the processed oil shale and determine potential changes in these properties caused by disposal and weathering by natural and simulated climatic conditions; assess the use of previously developed computer model(s) to describe the infiltration, unsaturated movement, redistribution, and drainage of water in disposed processed oil shale; evaluate the stability of field scale processed oil shale solid waste embankments using computer models

  11. Comments on ''Use of conditional simulation in nuclear waste site performance assessment'' by Carol Gotway

    Downing, D.J.

    1993-01-01

    This paper discusses Carol Gotway's paper, ''The Use of Conditional Simulation in Nuclear Waste Site Performance Assessment.'' The paper centers on the use of conditional simulation and the use of geostatistical methods to simulate an entire field of values for subsequent use in a complex computer model. The issues of sampling designs for geostatistics, semivariogram estimation and anisotropy, turning bands method for random field generation, and estimation of the comulative distribution function are brought out

  12. Estimation of the conditioning and storage costs of low- and intermediate-level solid radioactive wastes

    Lo Moro, A.; Panciatici, G.

    1977-01-01

    The conditioning and storage costs of low- and intermediate-level solid radioactive wastes are analyzed. The cost of direct labour is assumed as the reference cost for their computation and the storage cost is considered as resulting from the contract cost ''una tantum'' and from the leasing cost. As an example, the cost trends are reported, relevant to the solution adopted at CAMEN (conditioning in concrete containers and storage on concrete open-air bed)

  13. Condition assessment of the Los Alamos National Laboratory radioactive liquid waste collection system

    Edgemon, G.L.; Moss, W.D.; Worland, V.P.

    2004-01-01

    The radioactive liquid waste collection system (RLWCS) at Los Alamos National Laboratory (LANE) is a site-wide double-encased piping system installed in 1982 that allows radioactive liquid waste (RLW) producing facilities to gravity drain their waste to the radioactive liquid waste treatment facility (RLWTF) through a system of underground high-density polyethylene (HDPE) pipes and vaults. The RLWCS stretches approximately four miles and typically receives approximately 10,000 gallons of RLW per day for treatment at the RLWTF. Uncertainty of the current condition of the RLWCS was recently identified as a potential risk to the future continued availability of the RLW treatment function. A condition assessment was performed in April 2004 to evaluate the risks and estimate the remaining useful life of the existing RLWCS. Several representative and 'worst-case' RLWCS primary piping sections and their associated inspection vaults were selected for direct visual assessment, remote borescopic examination, and in-situ durometer testing. This field investigation combined with an RLWCS materials compatibility review showed that the primary piping of the RLWCS is in relatively good condition, with only a few noteworthy areas of degradation.

  14. Treatment and conditioning of radioactive waste solution by natural clay minerals

    El-Dessouky, M.I.; El-Massry, E.H.; Khalifa, S.M.; Aly, H.F.

    1999-01-01

    Natural inorganic exchangers. Was used to remove caesium, cobalt and europium using zinc sulfate as coagulant also different clay minerals. These calys include, feldrspare, aswanly, bentionite, hematite, mud, calcite, basalt, magnetite, kaoline sand stone, limonite and sand. The factros affecting the removal process namely PH, particle size, temperature and weight of the clay have been studied. Highest removal for Cs-137, Co-60 and Eu-152 and 154 was achived by asswanly and bentonite. Sand stone is more effective than the other clays. Removal of Cs-137 from low level waste solution is in the order the sequence, aswanly (85.5%)> bentonite (82.2%)> sandstone (65.4%). Solidified cement products have been evaluated to determine optimum conditions of mixing most sludges contained clays by testing mechanical strength and leaching rates of the waste products. The solidified waste forms were found more acceptable for handing, storage and ultimate disposal

  15. French practice and trends in the treatment and conditioning of PWR liquid effluents and solid wastes

    Celeri, J.J.; Pottier, P.; Sousselier, Y.

    1982-01-01

    From the early stages of the development of the nuclear industry in France, it has been decided to avoid radioactive effluent release by treatment, conditioning and storage of the wastes. It was not possible, when choosing this option, to reach the optimum from the beginning for the whole management system. The selection of a treatment process requires a precise knowledge of the nature, the composition and the arisings of radioactive wastes and these data are only available when commercial size reactors are in operation. To solve this problem, a close collaboration has been developed between the nuclear station operators and the R and D laboratories in charge of studying new treatment methods. This cooperation is a fruitful permanent exchange giving precise data about the waste, results of treatment operation on the industrial units, allowing modification in the installations to improve their efficiency and sometimes, resulting in new trends for the research program

  16. Mechanical-biological waste conditioning with controlled venting - the Meisenheim mechanical-biological waste conditioning plant; Mechanisch-biologische Restabfallbehandlung nach dem Kaminzugverfahren - MBRA Meisenheim

    Hangen, H.O. [Abfallwirtschaftsbetrieb Landkreis Bad Kreuznach, Bad Kreuznach (Germany)

    1998-12-31

    The decision of the rural district of Bad Kreuznach to propose creating facilities for mechanical-biological waste conditioning at the new northern Meisenheim landfill was consistent and correct. It will ensure that the material deposited at this new, state-of-the-art landfill is organically `lean` and can be deposited with a high density. Preliminary sifting of the material prior to depositing safeguards that no improper components are inadvertently included. Three years of operation warrant the statement that waste components that cannot be appropriately biologically conditioned should be eliminated prior to rotting. (orig.) [Deutsch] Die Entscheidung des Landkreises Bad Kreuznach, der neu eingerichteten Norddeponie Meisenheim eine MBRA vorzuschlaten, war auf jeden Fall konsequent und richtig. Es ist damit sicher gestellt, dass in diesem neuen nach dem Stand der Technik eingerichteten Deponiebereich von Anfang an ein Material eingelagert wird, das `organisch abgemagert` ist und mit hoher Einbaudichte eingebaut werden kann. Die Sichtung des gesamten Deponie-Inputs in der Vorsortierhalle gibt ein Stueck Sicherheit, dass keine nicht zugelassenen Stoffe verdeckt dem Ablagerungsbereich der Deponie zugefuehrt werden. Nach mehr als 3 Jahren Betriebszeit kann festgestellt werden, dass biologisch nicht sinnvoll behandelbare Abfallbestandteile vor dem Rotteprozess abgetrennt werden sollten. (orig.)

  17. Social life and sanitary risks: evolutionary and current ecological conditions determine waste management in leaf-cutting ants.

    Farji-Brener, Alejandro G; Elizalde, Luciana; Fernández-Marín, Hermógenes; Amador-Vargas, Sabrina

    2016-05-25

    Adequate waste management is vital for the success of social life, because waste accumulation increases sanitary risks in dense societies. We explored why different leaf-cutting ants (LCA) species locate their waste in internal nest chambers or external piles, including ecological context and accounting for phylogenetic relations. We propose that waste location depends on whether the environmental conditions enhance or reduce the risk of infection. We obtained the geographical range, habitat and refuse location of LCA from published literature, and experimentally determined whether pathogens on ant waste survived to the high soil temperatures typical of xeric habitats. The habitat of the LCA determined waste location after phylogenetic correction: species with external waste piles mainly occur in xeric environments, whereas those with internal waste chambers mainly inhabit more humid habitats. The ancestral reconstruction suggests that dumping waste externally is less derived than digging waste nest chambers. Empirical results showed that high soil surface temperatures reduce pathogen prevalence from LCA waste. We proposed that LCA living in environments unfavourable for pathogens (i.e. xeric habitats) avoid digging costs by dumping the refuse above ground. Conversely, in environments suitable for pathogens, LCA species prevent the spread of diseases by storing waste underground, presumably, a behaviour that contributed to the colonization of humid habitats. These results highlight the adaptation of organisms to the hygienic challenges of social living, and illustrate how sanitary behaviours can result from a combination of evolutionary history and current environmental conditions. © 2016 The Author(s).

  18. Selection of appropriate conditioning matrices for the safe disposal of radioactive waste

    Vance, E.R.

    2002-01-01

    The selection of appropriate solid conditioning matrices or wasteforms for the safe disposal of radioactive waste is dictated by many factors. The overriding issue is that the matrix incorporating the radionuclides, together with a set of engineered barriers in a near-surface or deep geological repository, should prevent significant groundwater transport of radionuclides to the biosphere. For high-level waste (HLW) from nuclear fuel reprocessing, the favored matrices are glasses, ceramics and glass-ceramics. Borosilicate glasses are presently being used in some countries, but there are strong scientific arguments why ceramics based on assemblages of natural minerals are advantageous for HLW. Much research has been carried out in the last 40 years around the world, and different matrices are more suitable than others for a given waste composition. However a major stumbling block for HLW immobilisation is the mall number of approved geological repositories for such matrices. The most appropriate matrices for Intermediate and low-level wastes are contentious and the selection criteria are not very well defined. The candidate matrices for these latter wastes are cements, bitumen, geopolymers, glasses, glass-ceramics and ceramics. After discussing the pros and cons of various candidate matrices for given kinds of radioactive wastes, the SYNROC research program at ANSTO will be briefly surveyed. Some of the potential applications of this work using a variety of SYNROC derivatives will be given. Finally the basic research program at ANSTO on radioactive waste immobilisation will be summarised. This comprises mainly work on solid state chemistry to understand ionic valences and co-ordinations for the chemical design of wasteforms, aqueous durability to study the pH and temperature dependence of solid-water reactions, radiation damage effects on structure and solid-water reactions. (Author)

  19. Improvement of storage conditions and closure of the radioactive waste repository - Rozan

    Dutton, L.M.C.; Pacey, N.R.; Buckley, M.J.; Thomson, J.G.; Miller, W.; Barraclough, I.; Tomczak, W.; Mitrega, J.; Smietanski, L.

    2005-01-01

    The Rozan repository is a near-surface repository on the site of an ex-military fort, operated by Radioactive Waste Management Plant (RWMP). Solid or encapsulated waste is consigned to the repository. Low- and medium-activity waste produced in Poland is collected, processed, solidified and prepared for disposal at the Swierk facility. The waste is currently stored or disposed of within the fort structures, these have robust concrete walls, that provide both shielding and containment. The project, funded by the European Commission through the Phare Programme, aimed to improve the storage conditions and determine a strategy for closure achieving two key results; Stakeholder agreement to a strategy for the management and closure of the repository, and; Approval by the National Atomic Energy Agency of the safety case for the selected strategy. The strategy was selected using a multi-criteria analysis methodology at workshops that involved experts, regulators and other stakeholders. The selected strategy proposed that the waste in Facilities 3A and 8 should be left in situ and these facilities should continue to operate until the repository is closed. The waste in Rooms K7 to K9 of Facility 1 and in Facilities 2 and 3 should be retrieved, assayed, treated and packaged prior to redisposal. The short-lived waste that is retrieved from Rooms K7 to K9 of Facility 1 and Facilities 2 and 3 should be emplaced in Facility 8 subject to acceptance by the NAEA of the dose of 0.3mSv/y that might occur at long times in the future from a very unlikely scenario. When operations at the repository end, Facilities 3A and 8 should be covered with a multi-layer cap. Following selection of the strategy, assessment work was undertaken to support the production of the suite of safety cases. (author)

  20. Formation of stable uranium(VI) colloidal nanoparticles in conditions relevant to radioactive waste disposal.

    Bots, Pieter; Morris, Katherine; Hibberd, Rosemary; Law, Gareth T W; Mosselmans, J Frederick W; Brown, Andy P; Doutch, James; Smith, Andrew J; Shaw, Samuel

    2014-12-09

    The favored pathway for disposal of higher activity radioactive wastes is via deep geological disposal. Many geological disposal facility designs include cement in their engineering design. Over the long term, interaction of groundwater with the cement and waste will form a plume of a hyperalkaline leachate (pH 10-13), and the behavior of radionuclides needs to be constrained under these extreme conditions to minimize the environmental hazard from the wastes. For uranium, a key component of many radioactive wastes, thermodynamic modeling predicts that, at high pH, U(VI) solubility will be very low (nM or lower) and controlled by equilibrium with solid phase alkali and alkaline-earth uranates. However, the formation of U(VI) colloids could potentially enhance the mobility of U(VI) under these conditions, and characterizing the potential for formation and medium-term stability of U(VI) colloids is important in underpinning our understanding of U behavior in waste disposal. Reflecting this, we applied conventional geochemical and microscopy techniques combined with synchrotron based in situ and ex situ X-ray techniques (small-angle X-ray scattering and X-ray adsorption spectroscopy (XAS)) to characterize colloidal U(VI) nanoparticles in a synthetic cement leachate (pH > 13) containing 4.2-252 μM U(VI). The results show that in cement leachates with 42 μM U(VI), colloids formed within hours and remained stable for several years. The colloids consisted of 1.5-1.8 nm nanoparticles with a proportion forming 20-60 nm aggregates. Using XAS and electron microscopy, we were able to determine that the colloidal nanoparticles had a clarkeite (sodium-uranate)-type crystallographic structure. The presented results have clear and hitherto unrecognized implications for the mobility of U(VI) in cementitious environments, in particular those associated with the geological disposal of nuclear waste.

  1. Conditioning matrices from high level waste resulting from pyrochemical processing in fluorine salt

    Grandjean, Agnes; Advocat, Thierry; Bousquet, Nicolas; Jegou, Christophe

    2007-01-01

    Separating the actinides from the fission products through reductive extraction by aluminium in a LiF/AlF 3 medium is a process investigated for pyrometallurgical reprocessing of spent fuel. The process involves separation by reductive salt-metal extraction. After dissolving the fuel or the transmutation target in a salt bath, the noble metal fission products are first extracted by contacting them with a slightly reducing metal. After extracting the metal fission products, then the actinides are selectively separated from the remaining fission products. In this hypothesis, all the unrecoverable fission products would be conditioned as fluorides. Therefore, this process will generate first a metallic waste containing the 'reducible' fission products (Pd, Mo, Ru, Rh, Tc, etc.) and a fluorine waste containing alkali-metal, alkaline-earth and rare earth fission products. Immobilization of these wastes in classical borosilicate glasses is not feasible due to the very low solubility of noble metals, and of fluoride in these hosts. Alternative candidates have therefore been developed including silicate glass/ceramic system for fluoride fission products and metallic ones for noble metal fission products. These waste-forms were evaluated for their confinement properties like homogeneity, waste loading, volatility during the elaboration process, chemical durability, etc. using appropriate techniques. (authors)

  2. Leaching behaviour of hazardous waste under the impact of different ambient conditions.

    Pecorini, Isabella; Baldi, Francesco; Bacchi, Donata; Carnevale, Ennio Antonio; Corti, Andrea

    2017-05-01

    The overall objective of this study is to provide an improved basis for the assessment of the leaching behaviour of waste marked as hazardous partly stabilised (European waste catalogue code 19 03 04 ∗ ). Four samples of hazardous partly stabilised waste were subjected to two leaching tests: up-flow column tests and batch equilibrium tests. The research was carried out in two directions: the first aims at comparing the results of the two experimental setups while the second aims at assessing the impact of different ambient conditions on the leaching behaviour of waste. Concerning this latter objective the effect of mesophilic temperature, mechanical constraints and acid environment were tested through column percolation tests. Results showed no significant differences between batch and column leaching test outcomes when comparing average concentrations calculated at a liquid to solid ratio of 10:1 l kg -1  TS. Among the tested ambient conditions, the presence of an acid environment (pH=4.5) accelerated the leaching process resulting in a higher cumulative released quantity measured on the majority of the investigated polluting substances. On the contrary, the effect of temperature and mechanical constraints seemed to not affect the process showing final contents even lower than values found for the standard test. This result was furthermore confirmed by the application of the principal component analysis. Copyright © 2016 Elsevier Ltd. All rights reserved.

  3. Comparison of steam sterilization conditions efficiency in the treatment of Infectious Health Care Waste.

    Maamari, Olivia; Mouaffak, Lara; Kamel, Ramza; Brandam, Cedric; Lteif, Roger; Salameh, Dominique

    2016-03-01

    Many studies show that the treatment of Infectious Health Care Waste (IHCW) in steam sterilization devices at usual operating standards does not allow for proper treatment of Infectious Health Care Waste (IHCW). Including a grinding component before sterilization allows better waste sterilization, but any hard metal object in the waste can damage the shredder. The first objective of the study is to verify that efficient IHCW treatment can occur at standard operating parameters defined by the contact time-temperature couple in steam treatment systems without a pre-mixing/fragmenting or pre-shredding step. The second objective is to establish scientifically whether the standard operation conditions for a steam treatment system including a step of pre-mixing/fragmenting were sufficient to destroy the bacterial spores in IHCW known to be the most difficult to treat. Results show that for efficient sterilization of dialysis cartridges in a pilot 60L steam treatment system, the process would require more than 20 min at 144°C without a pre-mixing/fragmenting step. In a 720L steam treatment system including pre-mixing/fragmenting paddles, only 10 min at 144°C are required to sterilize IHCW proved to be sterilization challenges such as dialysis cartridges and diapers in normal conditions of rolling. Copyright © 2016 Elsevier Ltd. All rights reserved.

  4. The importance of thermal loading conditions to waste package performance at Yucca Mountain

    Buscheck, T.A.; Nitao, J.J.

    1994-10-01

    Temperature and relative humidity are primary environmental factors affecting waste package corrosion rates for the potential repository in the unsaturated zone at Yucca Mountain, Nevada. Under ambient conditions, the repository environment is quite humid. If relative humidity is low enough (<70%), corrosion will be minimal. Under humid conditions, corrosion is reduced if the temperature is low (<60 C). Using the V-TOUGH code, the authors model thermo-hydrological flow to investigate the effect of repository heat on temperature and relative humidity in the repository for a wide range of thermal loads. These calculations indicate that repository heat may substantially reduce relative humidity on the waste package, over hundreds of years for low thermal loads and over tens of thousands of year for high thermal loads. Temperatures associated with a given relative humidity decrease with increasing thermal load. Thermal load distributions can be optimized to yield a more uniform reduction in relative humidity during the boiling period

  5. Methods for conditioning wastes from spent fuel cans and dissolver residues

    De Regge, P.; Loida, A.; Schmidt-Hansberg, T.; Sombret, C.

    1985-04-01

    Several methods for conditioning spent fuel decladding hulls or dissolver residues have been considered in various countries of the European Community. Five of these methods use embedding technique with or without prior compaction: they are based on incorporation in metallic alloys, glass, ceramics, cements and metals or graphite compounds. A sixth one consists in melting the decladding materials. The corresponding research programs have been pursued to varying states of progress with regard to demonstrating their feasibility on an industrial scale and the use of genuine wastes in bench scale experiments. The properties of the conditioned wastes have been investigated. Special attention has been paid to the corrosion resistance to various aqueous media as tap water, brine or clayey water. Although no categorical conclusion can be drawn from the initial results, the available finding provide a basis for assessing the different processes [fr

  6. The conditioning of radioactive waste by bitumen; Conditionnement des dechets radioactifs par le bitume

    Rodier, J; Scheidhauer, J; Malabre, M [Commissariat a l' Energie Atomique, Chusclan (France). Centre de Production de Plutonium de Marcoule

    1961-07-01

    The separation of radioactive sludge and waste by bitumen is studied. Results are given concerning various trials carried out on the lixiviation of the final product by water as a function of the pH, of the time, and of the composition. The conditions for carrying out this process of coating the waste are controlled from a radioactive point of view. (author) [French] L'isolement de boues radioactives et de dechets par le bitume est etudie. Les resultats de divers essais portant sur la lixiviation par l'eau du produit fini en fonction du pH, du temps et de la composition sont exposes. Les conditions de realisation de l'enrobage sont controlees au point de vue du risque radioactif. (auteur)

  7. Alkaline degradation of organic materials contained in TRU wastes under repository conditions

    Otsuka, Yoshiki; Banba, Tsunetaka

    2007-09-01

    Alkaline degradation tests for 9 organic materials were conducted under the conditions of TRU waste disposal: anaerobic alkaline conditions. The tests were carried out at 90degC for 91 days. The sample materials for the tests were selected from the standpoint of constituent organic materials of TRU wastes. It has been found that cellulose and plastic solidified products are degraded relatively easily and that rubbers are difficult to degrade. It could be presumed that the alkaline degradation of organic materials occurs starting from the functional group in the material. Therefore, the degree of degradation difficulty is expected to be dependent on the kinds of functional group contained in the organic material. (author)

  8. THE EFFECT OF DIFFERENT EXPOSURE CONDITIONS ON THE CHARACTERISTICS OF THE MINERAL MATRICES STABILIZING HAZARDOUS WASTE

    Anna Król

    2016-05-01

    Full Text Available Mineral binders are more and more often used in the difficult process of disposal of inorganic hazardous waste containing heavy metals. Composites solidifying hazardous waste are deposited in the environment, which exposes them to the interaction of many variable factors. The paper presents the effect of different exposure conditions on physical and mechanical properties of concrete stabilizing galvanic sewage sludge (GO. The effect of the cyclic freezing and thawing, carbon dioxide (carbonation and high temperatures (200 °C, 400 °C, 600 °C on the properties of stabilizing matrices has been described. The results, in most cases, show a loss of durability of composites solidifying sewage sludge (GO by the influence of external conditions.

  9. Denitration and chemical precipitation of medium level liquid wastes and conditioning of high level wastes from low level liquid wastes by a roll dryer and subsequent vitrification

    Halaszovich, S.; Dix, S.; Harms, R.

    1987-01-01

    Medium level liquid waste (MAW) from the reprocessing need after being fixed in cement an additional shielding to meet required radiation limits for handling and transportation. Normally this shielding consists of concrete and its weight and volume is several times higher than that of the waste product itself. By means of caesium separation using nickel-potassium-hexacyanoferrate and after few years of interim storage waiting for the decay of Ruthenium and Antimony the activities will be reduced below permissible values. (13 MBq/l in waste solution for Cs, 28 MBq/l for Sb and 34 MBq/l for Ru). Below these limits there is no need for additional shielding after cementation in a 400 l drum. Experimental results show, that Caesium can be precipitated and separated effectively not only in laboratory but also in a larger scale under hot cell conditions. The process investigated in this work has been developed from the FIPS process for vitrification of highly radioactive fission product solutions. It consists of: denitration, precipitation, sludge separation, drying and melting

  10. Why cachexia kills: examining the causality of poor outcomes in wasting conditions

    Kalantar-Zadeh, Kamyar; Rhee, Connie; Sim, John J.; Stenvinkel, Peter; Anker, Stefan D.; Kovesdy, Csaba P.

    2013-01-01

    Weight loss is the hallmark of any progressive acute or chronic disease state. In its extreme form of significant lean body mass (including skeletal muscle) and fat loss, it is referred to as cachexia. It has been known for millennia that muscle and fat wasting leads to poor outcomes including death. On one hand, conditions and risk factors that lead to cachexia and inadequate nutrition may independently lead to increased mortality. Additionaly, cachexia per se, withdrawal of nutritional supp...

  11. Assessment of potential doses to workers during postulated accident conditions at the Waste Isolation Pilot Plant

    Hoover, M.D.; Newton, G.J.; Farrell, R.F.

    1996-01-01

    This qualitative hazard evaluation systematically assessed potential doses to workers during postulated accident conditions at the U.S. Department of Energy's Waste Isolation Pilot Plant (WIPP). Postulated accidents included the spontaneous ignition of a waste drum, puncture of a waste drum by a forklift, dropping of a waste drum from a forklift, and simultaneous dropping of seven drums during a crane failure. The descriptions and estimated frequencies of occurrence for these accidents were developed by the Hazard and Operability Study for CH TRU Waste Handling System (WCAP 14312). The estimated materials at risk, damage ratios, airborne release fractions and respirable fractions for these accidents were taken from the 1995 Safety Analysis Report (SAR) update and from the DOE handbook Airborne Release Fractions/Rates and Respirable Fractions for Nonreactor Nuclear Facilities (DOE-HDBK-3010-94). A Monte Carlo simulation was used to estimate the range of worker exposures that could result from each accident. Guidelines for evaluating the adequacy of defense-in-depth for worker protection at WIPP were adopted from a scheme presented by the International Commission on Radiological Protection in its publication on Protection from Potential Exposure: A Conceptual Framework (ICRP Publication 64). Probabilities of exposures greater than 5, 50, and 300 rem were less than 10 -2 , 10 -4 , and 10 -6 per year, respectively. In conformance with the guidance of DOE standard 3009-94, Appendix A (draft), we emphasize that use of these evaluation guidelines is not intended to imply that these numbers constitute acceptable limits for worker exposure under accident conditions. However, in conjunction with the extensive safety assessment in the 1995 SAR update, these results indicate that the Carlsbad Area Office strategy for the assessment of hazards and accidents assures the protection of workers, as well as members of the public and the environment

  12. Uranium, thorium and trace elements in geologic occurrences as analogues of nuclear waste repository conditions

    Wollenberg, H.A.; Brookins, D.G.; Cohen, L.H.; Flexser, S.; Abashian, M.; Murphy, M.; Williams, A.E.

    1984-01-01

    Contact zones between intrusive rocks and tuff, basalt, salt and granitic rock were investigated as possible analogues of nuclear waste repository conditions. Results of detailed studies of contacts between quartz monzonite of Laramide age, intrusive into Precambrian gneiss, and a Tertiary monzonite-tuff contact zone indicate that uranium, thorium and other trace elements have not migrated significantly from the more radioactive instrusives into the country rock. Similar observations resulted from preliminary investigations of a rhyodacite dike cutting basalt of the Columbia River plateau and a kimberlitic dike cutting bedded salt of the Salina basin. This lack of radionuclide migration occurred in hydrologic and thermal conditions comparable to, or more severe than those expected in nuclear waste repository environments and over time periods of the order of concern for waste repositories. Attention is now directed to investigation of active hydrothermal systems in candidate repository rock types, and in this regard a preliminary set of samples has been obtained from a core hole intersecting basalt underlying the Newberry caldera, Oregon, where temperatures presently range from 100 to 265 0 C. Results of mineralogical and geochemical investigations of this core should indicate the alteration mineralogy and behavior of radioelements in conditions analogous to those in the near field of a repository in basalt

  13. Optimisation of treatment, storage and disposal strategies for (unconditioned and conditioned) radioactive waste

    Bealby, J.

    1989-03-01

    This study examines the trade-offs involved between unconditioned and conditioned waste storage, by investigating the effects of different cost and environmental minimisation strategies on radioactive waste treatment and disposal strategies. The costs and environmental impacts from storage (unconditioned and conditioned), conditioning, transport and disposal are examined. A single generic mixed Magnox/AGR site is investigated, assuming a moderate nuclear power growth scenario over the period 1986 to 2030. Assessments have been performed for four weighting sets which cover the range of views perceived to exist about the relative importance of cost and environmental impact reduction. The base case conditioning option considers the availability of a LLW low force compaction plant in 1986 and two ILW conditioning plants (cement encapsulation and dissolution) in 1990. A base case set of disposal options considers the options of disposal to shallow land and burial facility and deep cavity facilities. The study investigates the effect of deferring the opening dates of the conditioning plants. A set of sensitivity studies show that the assessments are robust to the assumptions and impact parameters used. (author)

  14. α-waste conditioning concepts on the basis of waste arisings, actinide distribution and their influence on final disposal products

    Krause, H.; Scheffler, K.

    1978-01-01

    Among the wastes arising from the reprocessing and Pu-fuel element fabrication plants, only seven waste streams contain the major part of the actinides going into the radioactive waste. It is shown that the liquid α-waste from fuel element fabrication, the high level liquid waste, and the active fraction of the medium level liquid waste can be incorporated into borosilicate glass. Wet combustion of solid burnable waste allows a relatively easy and complete recovery of plutonium. Leached hulls, sludges from feed clarification and solid non-combustible wastes can be incorporated into concrete. These treatment methods guarantee that only relatively small amounts of high quality α-bearing residues have to be disposed of

  15. Effect of boundary conditions on thermohydraulic behavior of clay buffer used in nuclear waste repository

    Arul Peter, A.; Murugesan, K.; Mamidi, Ganesh; Sharma, Umesh Kumar; Sharma, D. Akanshu; Arora, Puneet

    2010-01-01

    The use of nuclear energy is increasing dramatically in the world due to the fast depletion of fossil fuels, and hence the nuclear waste disposal and its short and long-term effects are of considerable importance. One of the options considered for nuclear waste disposal is underground nuclear waste repository facility. In this underground nuclear waste disposal system the waste filled canisters are placed in the rock surrounded by an engineered clay barrier and the whole system is buried in the geological formation, which serves as the natural or geological barrier. The important characteristic of the clay barrier is that it should not open up for radiation though it is continuously subjected to heat loading from the canisters. The heat and moisture transport mechanisms through the clay barrier plays an important role in deciding its mechanical strength. Clay behaves as an unsaturated porous material when it is used as a buffer material in nuclear waste facility. The governing equations for heat and moisture transfer through unsaturated porous media are coupled and nonlinear and hence they have to be solved using numerical solution technique. This paper reports the results of a numerical study on heat and moisture transport through a buffer layer made of clay as used in nuclear waste repository. Galerkin's weighted residual finite element method has been employed for the solution of the non-linear coupled governing equations used to represent the heat and moisture transport through unsaturated clay material. A detailed computational procedure has been established for the solution of the non-linear governing equations using Newton-Raphson technique. Initially the code has been validated with available experimental results. Then numerical simulation results were obtained for heat and moisture variations within the buffer material for Dirichlet temperature boundary conditions in the range, 50 deg C 2 2 , with an aim to simulate the boundary conditions which the clay

  16. Investigation of some factors affecting on release of radon-222 from phosphogypsum waste associated with phosphate ore processing.

    Hilal, M A; El Afifi, E M; Nayl, A A

    2015-07-01

    The aim of this study is oriented to investigate the influence of some physicochemical factors such as radium distribution, grain size, moisture content and chemical constituents on releases of radon-222 from the accumulated phosphogypsum (PG) waste. The emanation fraction, activity concentration in the pore and the surface exhalation rate of radon-222 in the bulk PG waste are 34.5 ± 0.3%, 238.6 ± 7.8 kBq m(-3) and 213 ± 6.9 mBq m(-2) s(-1), respectively. These values were varied and enhanced slightly in the fine grain sizes (F1 factor of 1.05 folds compared to the bulk residue. It was also found that release of radon from residue PG waste was controlled positively by radium (Ra-226), calcium (CaSO4) and strontium (SrO). About 67% of radon release attributed to the grain size below 0.5 mm, while 33% due to the large grain size above 0.5 mm. The emanation fraction of Rn-222 is increased with moisture content and the maximum emanation is ∼43% of moisture of 3-8%. It reduced slowly with the continuous increase in moisture till 20%. Due to PG waste in situ can be enhancing the background to the surround workers and/or public. Therefore, the environmental negative impacts due to release of Rn-222 can be minimized by legislation to restrict its civil uses, or increasing its moisture to ∼10%, or by the particle size separation of the fine fraction containing the high levels of Ra-226 followed by a suitable chemical treatment or disposal; whereas the low release amount can be diluted and used in cement industry, roads or dam construction. Copyright © 2015 Elsevier Ltd. All rights reserved.

  17. Study of the operational conditions for anaerobic digestion of urban solid wastes

    Castillo M, Edgar Fernando; Cristancho, Diego Edison; Victor Arellano, A.

    2006-01-01

    This paper describes an experimental evaluation of anaerobic digestion technology as an option for the management of organic solid waste in developing countries. As raw material, a real and heterogeneous organic waste from urban solid wastes was used. In the first experimental phase, seed selection was achieved through an evaluation of three different anaerobic sludges coming from wastewater treatment plants. The methanization potential of these sludges was assessed in three different batch digesters of 500 mL, at two temperature levels. The results showed that by increasing the temperature to 15 deg. C above room temperature, the methane production increases to three times. So, the best results were obtained in the digester fed with a mixed sludge, working at mesophilic conditions (38-40 deg. C). Then, this selected seed was used at the next experimental phase, testing at different digestion times (DT) of 25, 20 and 18 days in a bigger batch digester of 20 L with a reaction volume of 13 L. The conversion rates were registered at the lowest DT (18 days), reaching 44.9 L/kg -1 of wet waste day -1 . Moreover, DT also has a strong influence over COD removal, because there is a direct relationship between solids removal inside the reactor and DT

  18. The selective recycling of mixed plastic waste of polylactic acid and polyethylene terephthalate by control of process conditions

    Carné Sánchez, Arnau; Collinson, Simon R.

    2011-01-01

    The glycolysis of postconsumer polyethylene terephthalate (PET) waste was evaluated with catalysts of zinc acetate, zinc stearate and zinc sulfate, showing that zinc acetate was the most soluble and effective. The chemical recycling by solvolysis of polylactic acid (PLA) and PET waste in either methanol or ethanol was investigated. Zinc acetate as a catalyst was found to be necessary to yield an effective depolymerization of waste PLA giving lactate esters, while with the same reaction condit...

  19. Radiological impact of the storage of solid wastes from coal-fored power plants

    Hugon, J.; Caries, J.C.; Patellis, A.; Roussel, S.

    1983-01-01

    Solid wastes from the coal-fired power plant of GARDANNE are stared in piles, outside near the unit. The coal contains a high proportion of sulfur, so the storage pile is a very reducing middle. The radium coming from the ore, which is mostly retained in the bottom ashes, could then be solubilized again, by physicochemical processes, leached by the rain and reach the nearest population through the food-chain pathways. Leaching-tests where made with three sampling series. The measurement datas show that only 15% of the 226 Ra can be solved and that the Ra 226 observed concentrations in vegetal samples come mostly from transportation of dust by the wind [fr

  20. Characterization of ash melting behaviour at high temperatures under conditions simulating combustible solid waste gasification.

    Niu, Miaomiao; Dong, Qing; Huang, Yaji; Jin, Baosheng; Wang, Hongyan; Gu, Haiming

    2018-05-01

    To achieve high-temperature gasification-melting of combustible solid waste, ash melting behaviour under conditions simulating high-temperature gasification were studied. Raw ash (RA) and gasified ash (GA) were prepared respectively by waste ashing and fluidized bed gasification. Results of microstructure and composition of the two-ash indicated that GA showed a more porous structure and higher content of alkali and alkali earth metals among metallic elements. Higher temperature promoted GA melting and could reach a complete flowing state at about 1250°C. The order of melting rate of GA under different atmospheres was reducing condition > inert condition > oxidizing condition, which might be related to different existing forms of iron during melting and different flux content with atmosphere. Compared to RA, GA showed lower melting activity at the same condition due to the existence of an unconverted carbon and hollow structure. The melting temperature for sufficient melting and separation of GA should be at least 1250°C in this work.

  1. Non-fuel cycle radioactive waste policy in Turkey

    Izmir, A.I.; Uslu, I.

    2001-01-01

    be difficult to trace. The fundamental issue for which protection is required, is the prevention of over exposure of individuals or groups throughout the entire life cycle of sealed sources, lkitelli Accident in Istanbul (in 08.01.1999) shows the importance of life cycle of sealed source. Disused sealed sources which potentially represent medium and high radiological risks in Turkey are mainly Am-241, Ra-226, Kr-85, Co-60, lr-192 and Cs-137. According to 'The Radiation Protection Regulation' all spent sources have to be sent to the manufacturer. However, the spent sources which the manufacturer stopped its source related activities or the sources which were imported before the issue of the Regulation, are stored in Radioactive Waste Processing and Storage Facility (CWPSF) of Cekmece Nuclear Research and Training Center (CNRTC). Main radionuclides in the inventory of the Facility are Co-60, Cs-137, Am-240, Sr-90, Kr-85, Fe-55 respectively. Conclusion. Waste prevention and minimisation is an essential element of any radioactive waste management strategy. The objective of waste minimisation is to reduce the activity and the volume of wastes for storage, treatment and disposal. The environmental impact will also be reduced, as well as the costs associated with contaminated material management. Due to increasing number of radiation and nuclear related activities, the waste facility of CNRTC is now becoming insufficient to meet the storage demand of the country. TAEA is now in a position to establish a new radioactive waste management facility and studies are now being carried out on the selection of the best place for the final storage of processed radioactive wastes. Research and development studies in TAEA will continue in radioactive waste management with the aim of improving data, models, and concepts related to long-term safety of disposal of radioactive waste. (author)

  2. Treatment, conditioning and storage of solid alpha-bearing waste and cladding hulls. Paris, 5-7 December 1977

    1978-01-01

    A synthesis of the current practices and research and development work in the area of alpha-bearing waste and cladding hulls management is presented in 27 papers. After a review of national programmes, general management aspects of radioactive wastes are presented and different techniques are exposed, mainly incineration, volume reduction, conditioning concepts and cladding hulls

  3. The study on the recycle condition for existence of the decommissioning waste in the nuclear power station

    Hironaga, Michihiko; Ozaki, Sachio; Hirai, Mitsuyuki; Sakamoto, Hiroyuki; Usui, Tatsuo; Simizu, Yasuo; Ogane, Daisuke

    2000-01-01

    To establish the technique of the recycle for concrete waste, this paper describes the recycle condition for existence of the decommissioning concrete waste in the nuclear power plant and considers the durability of cask yard concrete constructed at about twenty years ago. The authors examine the recycle system of concrete in the power plant. (author)

  4. Probability, conditional probability and complementary cumulative distribution functions in performance assessment for radioactive waste disposal

    Helton, J.C.

    1996-03-01

    A formal description of the structure of several recent performance assessments (PAs) for the Waste Isolation Pilot Plant (WIPP) is given in terms of the following three components: a probability space (S st , S st , p st ) for stochastic uncertainty, a probability space (S su , S su , p su ) for subjective uncertainty and a function (i.e., a random variable) defined on the product space associated with (S st , S st , p st ) and (S su , S su , p su ). The explicit recognition of the existence of these three components allows a careful description of the use of probability, conditional probability and complementary cumulative distribution functions within the WIPP PA. This usage is illustrated in the context of the U.S. Environmental Protection Agency's standard for the geologic disposal of radioactive waste (40 CFR 191, Subpart B). The paradigm described in this presentation can also be used to impose a logically consistent structure on PAs for other complex systems

  5. Probability, conditional probability and complementary cumulative distribution functions in performance assessment for radioactive waste disposal

    Helton, J.C.

    1996-01-01

    A formal description of the structure of several recent performance assessments (PAs) for the Waste Isolation Pilot Plant (WIPP) is given in terms of the following three components: a probability space (S st , L st , P st ) for stochastic uncertainty, a probability space (S su , L su , P su ) for subjective uncertainty and a function (i.e., a random variable) defined on the product space associated with (S st , L st , P st ) and (S su , L su , P su ). The explicit recognition of the existence of these three components allows a careful description of the use of probability, conditional probability and complementary cumulative distribution functions within the WIPP PA. This usage is illustrated in the context of the US Environmental Protection Agency's standard for the geologic disposal of radioactive waste (40 CFR 191, Subpart B). The paradigm described in this presentation can also be used to impose a logically consistent structure on PAs for other complex systems

  6. Microbial Gas Generation Under Expected Waste Isolation Pilot Plant Repository Conditions: Final Report

    Gillow, J.B.; Francis, A.

    2011-07-01

    Gas generation from the microbial degradation of the organic constituents of transuranic (TRU) waste under conditions expected in the Waste Isolation Pilot Plant (WIPP) was investigated. The biodegradation of mixed cellulosic materials and electron-beam irradiated plastic and rubber materials (polyethylene, polyvinylchloride, hypalon, leaded hypalon, and neoprene) was examined. We evaluated the effects of environmental variables such as initial atmosphere (air or nitrogen), water content (humid ({approx}70% relative humidity, RH) and brine inundated), and nutrient amendments (nitogen phosphate, yeast extract, and excess nitrate) on microbial gas generation. Total gas production was determined by pressure measurement and carbon dioxide (CO{sub 2}) and methane (CH{sub 4}) were analyzed by gas chromatography; cellulose degradation products in solution were analyzed by high-performance liquid chromatography. Microbial populations in the samples were determined by direct microscopy and molecular analysis. The results of this work are summarized.

  7. Microbial Gas Generation Under Expected Waste Isolation Pilot Plant Repository Conditions: Final Report

    Gillow, J.B.; Francis, A.

    2011-01-01

    Gas generation from the microbial degradation of the organic constituents of transuranic (TRU) waste under conditions expected in the Waste Isolation Pilot Plant (WIPP) was investigated. The biodegradation of mixed cellulosic materials and electron-beam irradiated plastic and rubber materials (polyethylene, polyvinylchloride, hypalon, leaded hypalon, and neoprene) was examined. We evaluated the effects of environmental variables such as initial atmosphere (air or nitrogen), water content (humid (∼70% relative humidity, RH) and brine inundated), and nutrient amendments (nitogen phosphate, yeast extract, and excess nitrate) on microbial gas generation. Total gas production was determined by pressure measurement and carbon dioxide (CO 2 ) and methane (CH 4 ) were analyzed by gas chromatography; cellulose degradation products in solution were analyzed by high-performance liquid chromatography. Microbial populations in the samples were determined by direct microscopy and molecular analysis. The results of this work are summarized.

  8. Radon exposure at a radioactive waste storage facility.

    Manocchi, F H; Campos, M P; Dellamano, J C; Silva, G M

    2014-06-01

    The Waste Management Department of Nuclear and Energy Research Institute (IPEN) is responsible for the safety management of the waste generated at all internal research centers and that of other waste producers such as industry, medical facilities, and universities in Brazil. These waste materials, after treatment, are placed in an interim storage facility. Among them are (226)Ra needles used in radiotherapy, siliceous cake arising from conversion processes, and several other classes of waste from the nuclear fuel cycle, which contain Ra-226 producing (222)Rn gas daughter.In order to estimate the effective dose for workers due to radon inhalation, the radon concentration at the storage facility has been assessed within this study. Radon measurements have been carried out through the passive method with solid-state nuclear track detectors (CR-39) over a period of nine months, changing detectors every month in order to determine the long-term average levels of indoor radon concentrations. The radon concentration results, covering the period from June 2012 to March 2013, varied from 0.55 ± 0.05 to 5.19 ± 0.45 kBq m(-3). The effective dose due to (222)Rn inhalation was further assessed following ICRP Publication 65.

  9. Concentrations and environmental fate of Ra in cation-exchange regeneration brine waste disposed to septic tanks and accumulation in sludge, New Jersey Coastal Plain, USA

    Szabo, Z.; Jacobsen, E.; Kraemer, T.F.; Parsa, B.

    2008-01-01

    Concentrations of Ra in liquid and solid wastes generated from 15 softeners treating domestic well waters from New Jersey Coastal Plain aquifers (where combined Ra (226Ra plus 228Ra) concentrations commonly exceed 0.185 Bq L-1) were determined. Softeners, when maintained, reduced combined Ra about 10-fold (septic-tank effluents receiving brine waste were less than in the untreated ground waters. The maximum combined Ra concentration in aquifer sands (40.7 Bq kg-1 dry weight) was less than that in sludge from the septic tanks (range, 84-363 Bq kg-1), indicating Ra accumulation in sludge from effluent. The combined Ra concentration in sludge from the homeowners' septic systems falls within the range reported for sludge samples from publicly owned treatment works within the region.

  10. Characteristics of radioactive waste forms conditioned for storage and disposal: Guidance for the development of waste acceptance criteria

    1983-04-01

    This report attempts to review the characteristics of the individual components of the waste package, i.e. the waste form and the container, in order to formulate, where appropriate, quidelines for the development of practical waste acceptance criteria. Primarily the criteria for disposal are considered, but if more stringent criteria are expected to be necessary for storage or transportation prior to the disposal, these will be discussed. The report will also suggest test areas which will aid the development of the final waste acceptance criteria

  11. Treatment and conditioning of low-level radioactive waste in Belgium: initial operating results of the Cilva facility

    Monsch, O.; Renard, C.; Deckers, J.; Luycx, P.

    1995-01-01

    The Belgian National Radioactive Waste and Enriched Fissile Material Agency (ONDRAF), which is responsible for the management of all radioactive waste in Belgium, recently decided to commission the CILVA facility. Operation of this facility, which comprises a number of units for the treatment of low-level radwaste, has been contracted to ONDRAF's Belgoprocess subsidiary based at the Dessel site. A consortium comprising SGN and Fabricom was in charge of building the CILVA facility's waste preparation and conditioning (concrete solidification) units. The concrete solidification processes, which were devised and developed by SGN, have been qualified to secure ONDRAF certification of the process and the facility. This enabled active commissioning of the waste conditioning unit in mid-August 1994. Active commissioning of the waste preparation unit was carried out in several stages up to the beginning of 1995 in accordance with operating requirements. Initial operating results of the two units are presented. (author)

  12. Biomass waste carbon materials as adsorbents for CO2 capture under post-combustion conditions

    Elisa M Calvo-Muñoz

    2016-05-01

    Full Text Available A series of porous carbon materials obtained from biomass waste have been synthesized, with different morphologies and structural properties, and evaluated as potential adsorbents for CO2 capture in post-combustion conditions. These carbon materials present CO2 adsorption capacities, at 25 ºC and 101.3 kPa, comparable to those obtained by other complex carbon or inorganic materials. Furthermore, CO2 uptakes under these conditions can be well correlated to the narrow micropore volume, derived from the CO2 adsorption data at 0 ºC (VDRCO2. In contrast, CO2 adsorption capacities at 25 ºC and 15 kPa are more related to only pores of sizes lower than 0.7 nm. The capacity values obtained in column adsorption experiments were really promising. An activated carbon fiber obtained from Alcell lignin, FCL, presented a capacity value of 1.3 mmol/g (5.7 %wt. Moreover, the adsorption capacity of this carbon fiber was totally recovered in a very fast desorption cycle at the same operation temperature and total pressure and, therefore, without any additional energy requirement. Thus, these results suggest that the biomass waste used in this work could be successfully valorized as efficient CO2 adsorbent, under post-combustion conditions, showing excellent regeneration performance.

  13. The corrosion behavior of iron and aluminum under waste disposal conditions

    Fujisawa, R.; Cho, T.; Sugahara, K.; Takizawa, Y.; Hironaga, M.

    1997-01-01

    The generation of hydrogen gas from metallic waste in corrosive disposal environment is an important issue for the safety analysis of low-level radioactive waste disposal facilities in Japan. In particular iron and aluminum are the possibly important elements regarding the gas generation. However, the corrosion behavior of these metals has not been sufficiently investigated under the highly alkaline non-oxidizing disposal conditions yet. The authors studied the corrosion behavior of iron and aluminum under simulated disposal environments. The quantity of hydrogen gas generated from iron was measured in a closed cell under highly alkaline non-oxidizing conditions. The observed corrosion rate of iron in the initial period of immersion was 4 nm/year at 15 C, 20 nm/year at 30 C, and 200 nm/year at 45 C. The activation energy was found to be 100 kJ/mol from Arrhenius plotting of the above corrosion rates. The corrosion behavior of aluminum was studied under an environment simulating conditions in which aluminum was solidified with mortar. In the initial period aluminum corroded rapidly with a corrosion rate of 20 mm/year. However, the corrosion rate decreased with time, and after 1,000 hours the rate reached 0.001 to 0.01 mm/year. Thus the authors obtained data on hydrogen gas generation from iron and aluminum under the disposal environment relevant to the safety analysis of low-level radioactive disposal facilities in Japan

  14. Treatment and final conditioning of solid radioactive wastes; Traitement et conditionnement definitif des dechets radioactifs solides

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

    1960-07-01

    The storage of solid radioactive wastes on a site is so cumbersome and dangerous that we have developed a method of treatment and conditioning by means of which the volume of waste is considerably reduced and very long-lasting shielding can be provided. This paper describes the techniques adopted at Saclay, where the wastes are sheared, compressed and enveloped in concrete of variable thickness. The main part of the report is devoted to a description of the corresponding remote handling installation. (author) [French] L'encombrement et le danger que presentent sur un site le stockage de dechets radioactifs solides nous ont amenes a etudier un mode de traitement et de conditionnement permettant une sensible reduction du volume des dechets et une protection de tres longue duree. La presente communication expose les techniques adoptees a Saclay ou les dechets sont cisailles, comprimes et enrobes dans du beton d'epaisseur variable. La description de l'installation telecommandee correspondante fait l'objet principal de cette communication. (auteur)

  15. A radioactive waste transportation package monitoring system for normal transport and accident emergency response conditions

    Brown, G.S.; Cashwell, J.W.; Apple, M.L.

    1991-01-01

    Shipments of radioactive material (RAM) constitute but a small fraction of the total hazardous materials shipped in the United States each year. Public perception, however, of the potential consequences of a release from a transportation package containing RAM has resulted in significant regulation of transport operations, both to ensure the integrity of a package in accident conditions and to place operational constraints on the shipper. Much of this attention has focused on shipments of spent nuclear fuel and high level wastes which, although comprising a very small number of total shipments, constitute a majority of the total curies transported on an annual basis. This report discusses the shipment of these highly radioactive materials

  16. Beta-hydroxy-beta-methylbutyrate supplementation and skeletal muscle in healthy and muscle-wasting conditions.

    Holeček, Milan

    2017-08-01

    Beta-hydroxy-beta-methylbutyrate (HMB) is a metabolite of the essential amino acid leucine that has been reported to have anabolic effects on protein metabolism. The aims of this article were to summarize the results of studies of the effects of HMB on skeletal muscle and to examine the evidence for the rationale to use HMB as a nutritional supplement to exert beneficial effects on muscle mass and function in various conditions of health and disease. The data presented here indicate that the beneficial effects of HMB have been well characterized in strength-power and endurance exercise. HMB attenuates exercise-induced muscle damage and enhances muscle hypertrophy and strength, aerobic performance, resistance to fatigue, and regenerative capacity. HMB is particularly effective in untrained individuals who are exposed to strenuous exercise and in trained individuals who are exposed to periods of high physical stress. The low effectiveness of HMB in strength-trained athletes could be due to the suppression of the proteolysis that is induced by the adaptation to training, which may blunt the effects of HMB. Studies performed with older people have demonstrated that HMB can attenuate the development of sarcopenia in elderly subjects and that the optimal effects of HMB on muscle growth and strength occur when it is combined with exercise. Studies performed under in vitro conditions and in various animal models suggest that HMB may be effective in treatment of muscle wasting in various forms of cachexia. However, there are few clinical reports of the effects of HMB on muscle wasting in cachexia; in addition, most of these studies evaluated the therapeutic potential of combinations of various agents. Therefore, it has not been possible to determine whether HMB was effective or if there was a synergistic effect. Although most of the endogenous HMB is produced in the liver, there are no reports regarding the levels and the effects of HMB supplementation in subjects with

  17. Bio-hydrogen production from waste fermentation. Mixing and static conditions

    Gomez, X.; Cuetos, M.J.; Prieto, J.I.; Moran, A. [Chemical Engineering Dept. IRENA, University of Leon, Avda. de Portugal 41, 24071 Leon (Spain)

    2009-04-15

    One of the main disadvantages of the dark fermentation process is the cost associated with the stages needed for obtaining H{sub 2} producing microorganisms. Using anaerobic microflora in fermentation systems directly is an alternative which is gaining special interest when considering the implementation of large-scale plants and the use of wastes as substrate material. The performance of two H{sub 2} producing microflora obtained from different anaerobic cultures was studied in this paper. Inoculum obtained from a waste sludge digester and from a laboratory digester treating slaughterhouse wastes were used to start up H{sub 2} fermentation systems. Inoculum acclimatized to slaughterhouse wastes gave better performance in terms of stability. However, due to the limited availability of this seed material, further work was performed to study the behaviour of the inoculum obtained from the municipal wastewater treatment plant. The process was evaluated under static and mixing conditions. It was found that application of a low organic loading rate favoured the performance of the fermentation systems, and that agitation of the reacting mass could alleviate unsteady performance. Specific H{sub 2} production obtained was in the range of 19-26 L/kg SV{sub fed} with maximum peak production of 38-67 L/kg SV{sub fed}. Although the performance of the systems was unsteady, recovery could be achieved by suspending the feeding process and controlling the pH in the range of 5.0-5.5. Testing the recovery capacity of the systems under temperature shocks resulted in total stoppage of H{sub 2} production. (author)

  18. Radioactive wastes management in a radiochemistry laboratory

    Silva, Ana C.A.; Pereira, Wagner de S; Py Junior, Delcy de A.; Antunes, Ivan M.; Kelecom, Alphonse

    2009-01-01

    The Laboratorio de Monitoracao Ambiental (AMB) of the Unidade de Tratamento de Minerio (UTM) belonging to the Industrias Nucleares do Brasil is a chemical, radiochemical and radiometric laboratory, that analyses the natural radionuclides present in samples coming from the various installation of Industrias Nucleares do Brasil (INB). To minimize the radiological environmental impact, that laboratory has adopted a washing system of the chapel exhausting, that recirculate the washing water. These water can accumulate the radionuclides coming from the samples, that are liberated together the exhaustion gases from the chapels. Also, the water coming from the analyses and the sample releases (environmental and of the process) represent the liquid effluents of the AMB. The release of this effluent must pass by chemical and radiological criteria. From the radiological viewpoint, that release must be based on the Brazilian Nuclear Energy Commission (CNEN) regulations. This work try to establish the monitoring frequency, the radionuclides to be analysed, the form of liberation of those effluents, and the analytical techniques to be used. The radionuclides to be analysed will be U-nat, Ra-226 and Pb-210, of the uranium series, and the Th-232 and Ra-228, of the thorium series. The effluents must be monitored either before the release or, at least, twice a year. The effluents considered radioactive wastes, will be send to waste dam by the radioprotection service, or to the effluent treatment for controlled liberation for the environment

  19. Determining heavy metals in spent compact fluorescent lamps (CFLs) and their waste management challenges: Some strategies for improving current conditions

    Taghipour, Hassan; Amjad, Zahra; Jafarabadi, Mohamad Asghari; Gholampour, Akbar; Norouz, Prviz

    2014-01-01

    Highlights: • Heavy metals in spent compact fluorescent lamps (CFLs) determined. • Current waste management condition of CFLs in Iran assessed. • Currently, waste of CFLs is disposed by municipal waste stream in waste landfills. • We propose extended producer responsibility (EPR) for CFLs waste management. - Abstract: From environmental viewpoint, the most important advantage of compact fluorescent lamps (CFLs) is reduction of green house gas emissions. But their significant disadvantage is disposal of spent lamps because of containing a few milligrams of toxic metals, especially mercury and lead. For a successful implementation of any waste management plan, availability of sufficient and accurate information on quantities and compositions of the generated waste and current management conditions is a fundamental prerequisite. In this study, CFLs were selected among 20 different brands in Iran. Content of heavy metals including mercury, lead, nickel, arsenic and chromium was determined by inductive coupled plasma (ICP). Two cities, Tehran and Tabriz, were selected for assessing the current waste management condition of CFLs. The study found that waste generation amount of CFLs in the country was about 159.80, 183.82 and 153.75 million per year in 2010, 2011 and 2012, respectively. Waste generation rate of CFLs in Iran was determined to be 2.05 per person in 2012. The average amount of mercury, lead, nickel, arsenic and chromium was 0.417, 2.33, 0.064, 0.056 and 0.012 mg per lamp, respectively. Currently, waste of CFLs is disposed by municipal waste stream in waste landfills. For improving the current conditions, we propose by considering the successful experience of extended producer responsibility (EPR) in other electronic waste management. The EPR program with advanced recycling fee (ARF) is implemented for collecting and then recycling CFLs. For encouraging consumers to take the spent CFLs back at the end of the products’ useful life, a proportion of

  20. Determining heavy metals in spent compact fluorescent lamps (CFLs) and their waste management challenges: Some strategies for improving current conditions

    Taghipour, Hassan, E-mail: hteir@yahoo.com [Department of Environmental Health Engineering, Tabriz University of Medical Sciences, Tabriz (Iran, Islamic Republic of); Amjad, Zahra [Student Research Committee, Department of Environmental Health Engineering, Tabriz University of Medical Sciences, Tabriz (Iran, Islamic Republic of); Jafarabadi, Mohamad Asghari [Medical Education Research Center, Department of Statistics and Epidemiology, Tabriz University of Medical Sciences, Tabriz (Iran, Islamic Republic of); Gholampour, Akbar [Department of Environmental Health Engineering, Tabriz University of Medical Sciences, Tabriz (Iran, Islamic Republic of); Norouz, Prviz [Environmental Health Engineering, Shahid Beheshti University of Medical Sciences, Tehran (Iran, Islamic Republic of)

    2014-07-15

    Highlights: • Heavy metals in spent compact fluorescent lamps (CFLs) determined. • Current waste management condition of CFLs in Iran assessed. • Currently, waste of CFLs is disposed by municipal waste stream in waste landfills. • We propose extended producer responsibility (EPR) for CFLs waste management. - Abstract: From environmental viewpoint, the most important advantage of compact fluorescent lamps (CFLs) is reduction of green house gas emissions. But their significant disadvantage is disposal of spent lamps because of containing a few milligrams of toxic metals, especially mercury and lead. For a successful implementation of any waste management plan, availability of sufficient and accurate information on quantities and compositions of the generated waste and current management conditions is a fundamental prerequisite. In this study, CFLs were selected among 20 different brands in Iran. Content of heavy metals including mercury, lead, nickel, arsenic and chromium was determined by inductive coupled plasma (ICP). Two cities, Tehran and Tabriz, were selected for assessing the current waste management condition of CFLs. The study found that waste generation amount of CFLs in the country was about 159.80, 183.82 and 153.75 million per year in 2010, 2011 and 2012, respectively. Waste generation rate of CFLs in Iran was determined to be 2.05 per person in 2012. The average amount of mercury, lead, nickel, arsenic and chromium was 0.417, 2.33, 0.064, 0.056 and 0.012 mg per lamp, respectively. Currently, waste of CFLs is disposed by municipal waste stream in waste landfills. For improving the current conditions, we propose by considering the successful experience of extended producer responsibility (EPR) in other electronic waste management. The EPR program with advanced recycling fee (ARF) is implemented for collecting and then recycling CFLs. For encouraging consumers to take the spent CFLs back at the end of the products’ useful life, a proportion of

  1. Long Term Behaviour Evaluation of Cement Conditioning Matrices Used for Management of Radioactive Wastes at IFIN-HH

    Dragolici, F.

    2013-01-01

    The mechanical and structural characterization of the radioactive waste conditioning matrix is very important during the final disposal stage in the radioactive waste management cycle. The conditioning products should be a monolith with acceptable mechanical, chemical and physical properties that are maintained over an appropriate time such that the release of radioactivity from the waste form in the environment is minimized. The aim of this work is the XRD application for the phase identification of matrix that simulates the conditioned radioactive waste and the correlation with mechanical performance. The selected matrices for the study are normal cement with iron precipitates (hydroxide and phosphate), mineral additives (bentonite and volcanic tuff) and complexing agents (tartaric, citric and oxalic acids). The results obtained by this analysis give information about the chemical reactions between the radioactive precipitates and the hydrates, hydrolysis products of the cement. (author)

  2. Studies of transuranic waste storage under conditions expected in the Waste Isolation Pilot Plant (WIPP). Interim summary report, October 1, 1977-June 15, 1979

    Kosiewicz, S.T.; Barraclough, B.L.; Zerwekh, A.

    1980-01-01

    The major focus of the program has been on the gas generation potential of organic wastes produced by radiolytic and thermal degradation under simulated WIPP storage conditions. The effects of TRU contamination level, temperature, waste type, pressure, and exposure time on radiolysis are presented. In addition, results from preliminary experiments on processed sludge dewatering are discussed. A summary is presented here of the results of a detailed study of all retrievably stored TRU wastes present at LASL before January 1, 1978. The data indicate a gross volume for the LASL inventory of 1610 m 3 with a total weight of nearly 1.24 x 10 6 kg (1240 metric tonnes). The dominant radionuclide contents of the waste are plutonium (primarily 238 Pu) and americium

  3. Modeling of hydrologic conditions and solute movement in processed oil shale waste embankments under simulated climatic conditions

    Turner, J.P.; Hasfurther, V.

    1992-01-01

    The scope of the research program and the continuation is to study interacting hydrologic, geotechnical, and chemical factors affecting the behavior and disposal of combusted processed oil shale. The research combines bench-scale testing with large scale research sufficient to describe commercial scale embankment behavior. The large scale approach was accomplished by establishing five lysimeters, each 7.3 x 3.0 x 3.0 m deep, filled with processed oil shale that has been retorted and combusted by the Lurgi-Ruhrgas (Lurgi) process. Approximately 400 tons of Lurgi processed oil shale waste was provided by Rio Blanco Oil Shale Co., Inc. (RBOSC) through a separate cooperative agreement with the University of Wyoming (UW) to carry out this study. Three of the lysimeters were established at the RBOSC Tract C-a in the Piceance Basin of Colorado. Two lysimeters were established in the Environmental Simulation Laboratory (ESL) at UW. The ESL was specifically designed and constructed so that a large range of climatic conditions could be physically applied to the processed oil shale which was filled in the lysimeter cells

  4. Modeling of hydrologic conditions and solute movement in processed oil shale waste embankments under simulated climatic conditions

    Turner, J.P.; Reeves, T.L.; Skinner, Q.D.; Hasfurther, V.

    1992-11-01

    The scope of the original research program and of its continuation is to study interacting hydrologic, geotechnical, and chemical factors affecting the behavior and disposal of combusted processed oil shale. The research combines bench-scale testing with large-scale testing sufficient to describe commercial-scale embankment behavior. The large-scale testing was accomplished by constructing five lysimeters, each 7.3x3.0x3.0 m deep, filled with processed oil shale that has been retorted and combusted by the Lurgi-Ruhrgas (Lurgi) process (Schmalfield 1975). Approximately 400 tons of Lurgi processed oil shale waste was provided by Rio Blanco Oil Shale Co., Inc. to carry out this study. Three of the lysimeters were established at the RBOSC Tract C-a in the Piceance Basin near Rifle, Colorado. Two lysimeters were established in the Environmental Simulation Laboratory (ESL) at UW. The ESL was specifically designed and constructed so that a large range of climatic conditions could be physically applied to the processed oil shale which was placed in the lysimeter cells. This report discusses and summarizes results from scientific efforts conducted between October 1991 and September 1992 for Fiscal Year 1992

  5. Study on the conditions of bituminization of radioactive wastes and their influence on the stability of stored products

    Golinski, M.; Ksiazak, Z.

    1975-05-01

    Investigations carried out on a laboratory and semi-industrial scale showed that the Polish oxidised industrial bitumen P-60 was suitable for the solidification of liquid radioactive waste and particularly for non-concentrated post-precipitation sludges. The bitumen products were highly stable and were resistant to leaching by acids, salt solutions and water. Laboratory leach tests gave values similar to those obtained by others using different bitumen. By evaluating the sorption characteristics of the soil and the hydrogeological conditions existing at a proposed storage site, it was shown that the solidified wastes could be stored directly in the soil without further isolation from the soil water. Based on the liquid wastes arising from a nuclear power plant it has been shown that solidification of the wastes in bitumen will be cheaper than solidification of the same wastes using cement

  6. Determining heavy metals in spent compact fluorescent lamps (CFLs) and their waste management challenges: some strategies for improving current conditions.

    Taghipour, Hassan; Amjad, Zahra; Jafarabadi, Mohamad Asghari; Gholampour, Akbar; Norouz, Prviz

    2014-07-01

    From environmental viewpoint, the most important advantage of compact fluorescent lamps (CFLs) is reduction of green house gas emissions. But their significant disadvantage is disposal of spent lamps because of containing a few milligrams of toxic metals, especially mercury and lead. For a successful implementation of any waste management plan, availability of sufficient and accurate information on quantities and compositions of the generated waste and current management conditions is a fundamental prerequisite. In this study, CFLs were selected among 20 different brands in Iran. Content of heavy metals including mercury, lead, nickel, arsenic and chromium was determined by inductive coupled plasma (ICP). Two cities, Tehran and Tabriz, were selected for assessing the current waste management condition of CFLs. The study found that waste generation amount of CFLs in the country was about 159.80, 183.82 and 153.75 million per year in 2010, 2011 and 2012, respectively. Waste generation rate of CFLs in Iran was determined to be 2.05 per person in 2012. The average amount of mercury, lead, nickel, arsenic and chromium was 0.417, 2.33, 0.064, 0.056 and 0.012 mg per lamp, respectively. Currently, waste of CFLs is disposed by municipal waste stream in waste landfills. For improving the current conditions, we propose by considering the successful experience of extended producer responsibility (EPR) in other electronic waste management. The EPR program with advanced recycling fee (ARF) is implemented for collecting and then recycling CFLs. For encouraging consumers to take the spent CFLs back at the end of the products' useful life, a proportion of ARF (for example, 50%) can be refunded. On the other hand, the government and Environmental Protection Agency should support and encourage recycling companies of CFLs both technically and financially in the first place. Copyright © 2014 Elsevier Ltd. All rights reserved.

  7. Assessment of potential doses to workers during postulated accident conditions at the Waste Isolation Pilot Plant

    Hoover, M.D.; Farrell, R.F. [DOE, Carlsbad, NM (United States); Newton, G.J.

    1995-12-01

    The recent 1995 WIPP Safety Analysis Report (SAR) Update provided detailed analyses of potential radiation doses to members of the public at the site boundary during postulated accident scenarios at the U.S. Department of Energy`s Waste Isolation Pilot Plant (WIPP). The SAR Update addressed the complete spectrum of potential accidents associated with handling and emplacing transuranic waste at WIPP, including damage to waste drums from fires, punctures, drops, and other disruptions. The report focused on the adequacy of the multiple layers of safety practice ({open_quotes}defense-in-depth{close_quotes}) at WIPP, which are designed to (1) reduce the likelihood of accidents and (2) limit the consequences of those accidents. The safeguards which contribute to defense-in-depth at WIPP include a substantial array of inherent design features, engineered controls, and administrative procedures. The SAR Update confirmed that the defense-in-depth at WIPP is adequate to assure the protection of the public and environment. As a supplement to the 1995 SAR Update, we have conducted additional analyses to confirm that these controls will also provide adequate protection to workers at the WIPP. The approaches and results of the worker dose assessment are summarized here. In conformance with the guidance of DOE Standard 3009-94, we emphasize that use of these evaluation guidelines is not intended to imply that these numbers constitute acceptable limits for worker exposures under accident conditions. However, in conjunction with the extensive safety assessment in the 1995 SAR Update, these results indicate that the Carlsbad Area Office strategy for the assessment of hazards and accidents assures the protection of workers, members of the public, and the environment.

  8. Fabrication of a Sludge-Conditioning System for processing legacy wastes from the Gunite and Associated Tanks

    Randolph, J.D.; Lewis, B.E.; Farmer, J.R.; Johnson, M.A.

    2000-01-01

    The Sludge Conditioning System (SCS) for the Gunite and Associated Tanks (GAATs) is designed to receive, monitor, characterize and process legacy waste materials from the South Tank Farm tanks in preparation for final transfer of the wastes to the Melton Valley Storage Tanks (MVSTs), which are located at Oak Ridge National Laboratory. The SCS includes (1) a Primary Conditioning System (PCS) Enclosure for sampling and particle size classification, (2) a Solids Monitoring Test Loop (SMTL) for slurry characterization, (3) a Waste Transfer Pump to retrieve and transfer waste materials from GAAT consolidation tank W-9 to the MVSTs, (4) a PulsAir Mixing System to provide mixing of consolidated sludges for ease of retrieval, and (5) the interconnecting piping and valving. This report presents the design, fabrication, cost, and fabrication schedule information for the SCS

  9. Seasonal dependence of pigments number in Alhagi pseudalgahi leaves forming in conditions of high radiarion phone

    Orujova, J.R.; Dzhafarov, E.S.

    2006-01-01

    Full text: The activity circle of man includes also change of the radio ecological situation of environment, global increase of natural radiation phone, appearance of the local territories polluted with radio nuclides in result of technological processes, chemical pollution of air, water, land etc. As it's known, reaction of different plants to the impact of both natural, and anthropogenic stress factors isn't identical. This time change of the biometrical measures of plants' different organs, growth of their reproduction features, acceleration of biologically active matters synthesis etc. facts we elucidated in many works. The research works show that under external influence biological parameters don't change identically. Taking into account different character of the dependence of biochemical processes in plants on the external effects, and scarceness of research works on territories polluted by radio active industrial waste products, we can say that, respective experiments are needed. In the present work territory of iodine plant in Rome polluted with radio nuclides has been regarded as the experimental one. Within the plant area there was registered radiation phone totaling 800-1000 mkR/h. Ra 226, Th 232, U 238 and K 40 were detected as radio nucleids polluting the area. The work has spectrometrically identified number of the photosynthetic pigments of Alhagi Pseudalhagi plant formed both in conditions of high radiation phone, and in the control area in wild conditions. In result of measures there were calculated individual number of chlorophyllum a and b pigments playing photoreceptor role in photosynthesis process and having big importance for superior plants, ratio of chlorophyllum a to chlorophyllum b and the total. Besides, there has been designated number of carotinoids executing defensive function in chloroplasts. Results received show that in comparison with control in autumn season total number of green pigments is approximately two times lower than

  10. Probability, conditional probability and complementary cumulative distribution functions in performance assessment for radioactive waste disposal

    Helton, J.C. [Arizona State Univ., Tempe, AZ (United States)

    1996-03-01

    A formal description of the structure of several recent performance assessments (PAs) for the Waste Isolation Pilot Plant (WIPP) is given in terms of the following three components: a probability space (S{sub st}, S{sub st}, p{sub st}) for stochastic uncertainty, a probability space (S{sub su}, S{sub su}, p{sub su}) for subjective uncertainty and a function (i.e., a random variable) defined on the product space associated with (S{sub st}, S{sub st}, p{sub st}) and (S{sub su}, S{sub su}, p{sub su}). The explicit recognition of the existence of these three components allows a careful description of the use of probability, conditional probability and complementary cumulative distribution functions within the WIPP PA. This usage is illustrated in the context of the U.S. Environmental Protection Agency`s standard for the geologic disposal of radioactive waste (40 CFR 191, Subpart B). The paradigm described in this presentation can also be used to impose a logically consistent structure on PAs for other complex systems.

  11. The effect of cure conditions on the stability of cement waste forms after immersion in water

    Siskind, B.; Adams, J.W.; Clinton, J.H.; Piciulo, P.L.; McDaniel, K.

    1988-01-01

    We investigated the effects of curing conditions on the stability of cement-solidified ion-exchange resins after immersion in water. The test specimens consisted of partially depleted mixed-bed bead resins solidified in one of three vendor-supplied Portland I cement formulations, in a reference cement formulation, or in a gypsum-based binder formulation. We cured samples prepared using each formulation in sealed containers for periods of 7, 14, or 28 days as well as in air or with an accelerated heat cure prior to 90-day immersion in water. Two cement formulations exhibited apparent Portland-cement-like behavior, i.e., compressive strength increased or stabilized with increasing cure time. Two cement formulations exhibited behavior apparently unlike that of Portland cement, i.e., compressive strength decreased with increasing cure time. Such non-Portland-cement-like behavior is correlated with higher waste loadings. The gypsum-based formulation exhibited approximately constant compressive strength with cure time. Accelerated heat cures may not give compressive strengths representative of real-time cures. Some physical deterioration (cracking, spalling) of the waste form occurs during immersion

  12. The effect of cure conditions on the stability of cement waste forms after immersion in water

    Siskind, B.; Adams, J.W.; Clinton, J.H.; Piciulo, P.L.

    1988-01-01

    The authors investigated the effects of curing conditions on the stability of cement-solidified ion-exchange resins after immersion in water. The test specimens consisted of partially depleted mixed-bed bead resins solidified in one of three vendor-supplied Portland I cement formulations, in a reference cement formulation, or in a gypsum-based binder formulation. They cured samples prepared using each formulation in sealed containers for periods of 7, 14, or 28 days as well as in air or with an accelerated heat cure prior to 90-day immersion in water. Two cement formulations exhibited apparent Portland-cement-like behavior, i.e., compressive strength increased or stabilized with increasing cure time. Two cement formulations exhibited behavior apparently unlike that of Portland cement, i.e. compressive strength decreased with increasing cure time. Such non-Portland-cement-like behavior is correlated with higher waste loadings. The gypsum-based formulation exhibited approximately constant compressive strength with cure time. Accelerated heat cures may not give compressive strengths representative of real-time cures. Some physical deterioration (cracking, spalling) of the waste form occurs during immersion

  13. Evaluating inhibition conditions in high-solids anaerobic digestion of organic fraction of municipal solid waste.

    Schievano, Andrea; D'Imporzano, Giuliana; Malagutti, Luca; Fragali, Emilio; Ruboni, Gabriella; Adani, Fabrizio

    2010-07-01

    High-solids anaerobic digestion (HSAD) processes, when applied to different types of organic fractions of municipal solid waste (OFMSW), may easily be subjected to inhibition due to organic overloading. In this study, a new approach for predicting these phenomena was proposed based on the estimation of the putrescibility (oxygen consumption in 20 h biodegradation, OD(20)) of the organic mixtures undergoing the HSAD process. Different wastes exhibiting different putrescibility were subjected to lab-scale batch-HSAD. Measuring the organic loading (OL) as volatile solids (VS) was found unsuitable for predicting overload inhibition, because similar VS contents corresponded to both inhibited and successful trials. Instead, the OL calculated as OD(20) was a very good indicator of the inhibiting conditions (inhibition started for OD(20)>17-18 g O(2)kg(-1)). This new method of predicting inhibition in the HSAD process of diverse OFMSW may be useful for developing a correct approach to the technology in very different contexts. Copyright (c) 2010 Elsevier Ltd. All rights reserved.

  14. A study of operational conditions for anaerobic digestion of solid urban waste

    Édgar Femando Castillo M.

    2003-07-01

    Full Text Available This paper describes an experimental evaluation of anaerobic digestion as a technological option for organic solid-waste treatment in the city of Bucaramanga (Santander, Colombia. The inoculum was selected by evaluating three different anaerobic sludges. Sludge from UASB No. 2 digestor at the Waste Water Treatment Plant in Rio Frío (Girón, Santander was named [PTAR]. Sludge from the anaerobic biodigestor for pig manure treatment (Mesa de Los Santos, Santander was named [PIG] a 1:1 sludge mixture of [PTAR] and [PIG] sludges was named [MIX]. These sludges' methanisation behaviour was evaluated in three different 500 ml capacity CSTR digesters at mesophyllic and thermophyllic temperatures. 25,20 and 18 day retention times were studied in a 20 1 CSTR digester having a 131 reaction volume. The results showed that raising the temperature from 10 °C to 15 °C above normal reactor temperature increased methane production by 3 times. It was also seen that retention time had a strong influence on specific methane production since the best conversions were registered at the longest time recorded (25 days and it had a strong influence on DQO removal too. Another important condition for biodigestor optimal operation was agitation speed;this operation must be semi-continuous for maintaining methanisation process biological activity.

  15. Optimization on Pretreatment Conditions of Seaweed Liquid Waste for Bio ethanol Production

    Nur Zatul-Iffah Zakaria; Dachyar Arbain; Mohd Noor Ahmad; Mohd Irfan Hatim Mohamed Dzahir

    2015-01-01

    Seaweed liquid waste (SLW) from a non-conventional seaweed (Gracilaria sp.) drying process where the seaweed is ruptured and filter-squeezed has been investigated. The liquid contains proteins and minerals which potentially pollute the environment if it is not been properly treated. For that reason, this paper deals with study on the feasibility of SLW utilization as a feedstock for bio ethanol production. The fermentation of bio ethanol production was carried out by Saccharomyces cerevisiae in which ethanol produced was measured by gas chromatography. In order to increase its fermentable sugar content, the SLW was treated with dilute acid. Center composite design of response surface methodology (RSM) had been used to optimize the sugar content by varying the parameters involved in the dilute acid pretreatment conditions. These are sulphuric acid concentration (M), temperature (degree Celsius) and seaweed waste concentration (g/ ml). It was obtained that the R 2 value reached 0.97 indicating that the model is acceptable. The three parameters showed p-value less than 0.05 suggesting their significance interactions. The optimization resulted 25 times improvement of reducing sugar concentration. The reducing sugar resulting from the optimized pretreatment was later used as fermentation medium to produce ethanol up to 123.197 mg/ l. (author)

  16. Natural analogues to the conditions around a final repository for high-level radioactive waste

    Smellie, J.A.T.

    1984-12-01

    This report documents the proceedings resulting from a Workshop held at Lake Geneva, Wisconsin, USA, from 1-3 October, 1984. The theme of the Workshop was entitled 'Natural analogues to the conditions around a final repository for high-level radioactive waste', and was restricted to ultimate disposal in a crystalline bedrock environment. The Workshop provided an important first step in co-ordinating and focussing different national and individual interests and approaches towards natural analogue studies. One of the points highlighted at the concluding forum of the meeting was the necessity to first define the geochemical processes which are assumed to occur after disposal of the radioactive waste, and then locate suitable analogue systems which can be used to test the mechanisms of one, or a simple combination of these geochemical processes. Even accepting that the choice of which geochemical process(es) to be selected for validation will be sensitive to individual national disposal strategies, farfield radionuclide retardation mechanisms in the geosphere were considered to be a central topic of importance, and should therefore be given high priority. At this early stage in the development of natural analogue studies it was not possible to cover all the important aspects. In retrospect, the role of the models should have received more attention; bridging the gap between geoscientists and the modellers was seen as being of prime importance in future meetings of this nature. (author)

  17. The treatment and conditioning of transuranelement bearing wastes in the Federal Republic of Germany

    Krause, H.

    1986-01-01

    Transuranelement bearing wastes (TRU wastes) differ from other radioactive wastes (with the exception of high level wastes from reprocessing) primarily by the longevity and high radiotoxity of many of their radionuclides. The volumes and total TRU content of these wastes are still quite small. Due to the present absence of a repository for radioactive wastes in the FRG, no definitions of TRU wastes and no acceptance criteria for these wastes have been fixed so far. Anyway, as only waste disposal into deep geological formations is envisaged for the time being, the limits for the TRU content do not need to be as low as in countries practicing shallow land burial. During the experimental disposal in the Asse salt mine, wastes with a TRU-content <5μCi/g were considered as non-TRU waste. There is some probability that in the future a similar value may be fixed. The present practice in TRU waste management is primarily determined by this situation. However, this system is neither ideal from a fundamental point of view nor in the long range; and, therefore, research and development work is going on for the development of an advanced TRU waste management system which should meet the requirements of an industrial scale fast breeder fuel cycle, and also improve the acceptance of such a program by the public. (Auth.)

  18. The sorption and mechanical properties of the modified cement matrix used for conditioning of radioactive waste

    Dogaru, Daniela; Nuculae, Ortenzia; Jinescu, Gheorghita; Duliu, Octavian; Dogaru, Gheorghe

    2008-01-01

    Full text: Radioactive contaminant sorption onto concrete represents one of the most important retardation mechanisms in engineered barriers such as the conditioning matrix itself, concrete walls and concrete floors. During the life of a disposal facility for radioactive waste, the sorption properties as well as the mechanical properties of the cement are affected by both external and internal processes. The most important sorbing material present in concrete is the hydrated cement. The sorption data obtained for specific cement or cement mixes in general may be used to characterize a given cement type. In order to improve the mechanical and sorption properties of the cement matrix, different additives were used in the laboratory tests. The used additives are known to have good sorption properties. The paper describes the influence of the concentration of additives on the mechanical and sorption properties of the cement matrix. As radioactive contaminants 134 Cs, 60 Co, 3 H, 241 Am were used. (authors)

  19. Chemical conditions in the repository for low- and intermediate-level reactor waste

    Snellman, M.; Uotila, H.

    1984-01-01

    The chemical conditions in the proposed repositories for low- and intermediate-level reactor waste at Haestholmen (IVO) and Olkiluoto (TVO) have been discussed with respect to materials introduced into the repository, their possible long-term changes and interaction with groundwater flowing into the repository. The main possible groundwater-rock interactions have been discussed, as well as the role of micro-organisms, organic acids and colloids in the estimation of the barrier integrity. Experimental and theoretical studies have been performed on the basis of the natural groundwater compositions expected at the repository sites. Main emphasis is put on the chemical parameters which might influence the integrity of the different barriers in the repository as well as on the parameters which might effect the release and transport of radionuclides from the repository

  20. Radionuclide release from high level waste forms under repository conditions in clay or granite

    Godon, N.; Lanza, F.

    1990-01-01

    The behaviour of both fully active and simulated vitrified high level waste (HLW) has been studied under conditions that are likely to occur in future repositories in clay and granite. The simulated HLW was doped with Cs, Sr, Tc and the actinides and the leaching of these elements from the glass has been measured together with their concentrations in the water of the near-field and their distribution between the various components of the repository. The diffusion coefficients of several elements in Boom clay has also been measured. The results show that the concentrations of Tc and the actinides in the near-field of a repository will be very low and that the actinides will only diffuse very slowly away from the vicinity of the glass. 24 refs., 1 figs., 7 tabs

  1. Assessment of management alternatives for LWR wastes. Volume 6. Cost determination of the LWR waste management routes (treatment/conditioning/packaging/transport operations)

    Thiels, G.M.; Kowa, S.

    1993-01-01

    This report deals with the cost determination of a number of schemes for the treatment, conditioning, packaging, interim storage and transport operations of LWR wastes drawn up on the basis of Belgian, French and German practices in this particular area. In addition to the general procedure elaborated for determining, actualizing and scaling of plant and transport costs associated with the various schemes, in-depth calculations of each intermediate management stage are included in this report. This study is part of an overall theoretical exercise aimed at evaluating a selection of management routes for LWR waste based on economical and radiological criteria

  2. New system for the container conditioning of liquid waste in the German future finale repository 'Schacht Konrad'

    Starke, H.

    2012-01-01

    The full text of publication follows. On-site the NPP Gundremmingen liquid radioactive waste from the NPP water treatment plant is stored in resin or concentrate collecting tanks. These liquid wastes are cemented in containers in order to temporarily store them in the Bavarian interim storage Mitterteich until they are transported into final repository in 'Schacht Konrad'. With this new system liquid radioactive waste is for the first time conditioned directly into containers destined for final repository in 'Schacht Konrad'. Thus, a very secure and sustainable procedure was developed which also provides high profitability. The conditioning plant for resins and concentrate extracts the liquid waste from the respective collecting tank and transports the waste to the separation tank. This separation tank is dimensioned to ensure complete filling of a Konrad container with only one batch. Within the tank there is the option to adjust the suspensions solids content by either extracting supernatant water or by adding de-ionised water. The specific activity is analysed and after the radiologic data and the solids content are available, the containers are cemented. The required amount of cement is based on the solids content and is automatically added. In the mixer, cement and primary waste suspension are mixed. This mixture is filled into the Konrad container via the allocator. The allocator is a funnel-shaped inlet equipped with a movable tube which makes sure the mixture is evenly spread and also ensures optimal filling of the Konrad container. While filling is ongoing, the container is covered by a lowerable splash guard to avoid contamination. The room situation in Gundremmingen and the specific activities of the primary waste suspension make it necessary to disperse the plant to several rooms. Main components such as separation tanks and pumps are installed in shielded rooms. All activities are conducted remotely controlled and are supervised from the central

  3. Nitrous oxide production during nitrification from organic solid waste under temperature and oxygen conditions.

    Nag, Mitali; Shimaoka, Takayuki; Komiya, Teppei

    2016-11-01

    Landfill aeration can accelerate the biological degradation of organic waste and reduce methane production; however, it induces nitrous oxide (N2O), a potent greenhouse gas. Nitrification is one of the pathways of N2O generation as a by-product during aerobic condition. This study was initiated to demonstrate the features of N2O production rate from organic solid waste during nitrification under three different temperatures (20°C, 30°C, and 40°C) and three oxygen concentrations (5%, 10%, and 20%) with high moisture content and high substrates' concentration. The experiment was carried out by batch experiment using Erlenmeyer flasks incubated in a shaking water bath for 72 h. A duplicate experiment was carried out in parallel, with addition of 100 Pa of acetylene as a nitrification inhibitor, to investigate nitrifiers' contribution to N2O production. The production rate of N2O ranged between 0.40 × 10(-3) and 1.14 × 10(-3) mg N/g-DM/h under the experimental conditions of this study. The rate of N2O production at 40°C was higher than at 20°C and 30°C. Nitrification was found to be the dominant pathway of N2O production. It was evaluated that optimization of O2 content is one of the crucial parameters in N2O production that may help to minimize greenhouse gas emissions and N turnover during aeration.

  4. Microbial gas generation under expected Waste Isolation Pilot Plant repository conditions

    Francis, A.J.; Gillow, J.B.; Giles, M.R.

    1997-03-01

    Gas generation from the microbial degradation of the organic constituents of transuranic waste under conditions expected at the Waste Isolation Pilot Plant (WIPP) repository was investigated at Brookhaven National Laboratory. The biodegradation of mixed cellulosics (various types of paper) and electron-beam irradiated plastic and rubber materials (polyethylene, polyvinylchloride, neoprene, hypalon, and leaded hypalon) was examined. The rate of gas production from cellulose biodegradation in inundated samples incubated for 1,228 days at 30 C was biphasic, with an initial rapid rate up to approximately 600 days incubation, followed by a slower rate. The rate of total gas production in anaerobic samples containing mixed inoculum was as follows: 0.002 mL/g cellulose/day without nutrients; 0.004 mL/g cellulose/day with nutrients; and 0.01 mL/g cellulose/day in the presence of excess nitrate. Carbon dioxide production proceeded at a rate of 0.009 micromol/g cellulose/day in anaerobic samples without nutrients, 0.05 micromol/g cellulose/day in the presence of nutrients, and 0.2 micromol/g cellulose/day with excess nitrate. Adding nutrients and excess nitrate stimulated denitrification, as evidenced by the accumulation of N 2 O in the headspace (200 micromol/g cellulose). The addition of the potential backfill bentonite increased the rate of CO 2 production to 0.3 micromol/g cellulose/day in anaerobic samples with excess nitrate. Analysis of the solution showed that lactic, acetic, propionic, butyric, and valeric acids were produced due to cellulose degradation. Samples incubated under anaerobic humid conditions for 415 days produced CO 2 at a rate of 0.2 micromol/g cellulose/day in the absence of nutrients, and 1 micromol/g cellulose/day in the presence of bentonite and nutrients. There was no evidence of biodegradation of electron-beam irradiated plastic and rubber

  5. Optimization of the thermal conditions for processing hatchery waste eggs as meal for feed.

    Chiu, W Z; Wei, H W

    2011-05-01

    The purpose of this study was to optimize the thermal conditions for processing hatchery waste eggs (HWE) into rich feedstuff with lower electricity consumption by using response surface methodology. In the study, the effects of processing temperature and time on HWE meal (HWEM) quality and production were evaluated. As the results indicate, optimization was obtained when the processing lasted for 23 h at the fixed temperature of 65°C, resulting in higher protein digestibility in vitro (89.6%) and DM (88.5%) content of HWEM with lower electricity consumption (82.4 kWh/60 kg of HWE). No significant differences existed between the quality values predicted by mathematical formulae and those obtained through practical analyses in DM (87 vs. 88.5%), CP (39.2 vs. 38.3%), protein digestibility in vitro (90.7 vs. 89.6%), and electricity consumed (80.8 vs. 82.4 kWh/60 kg of HWE). Furthermore, the product derived from the optimized processing conditions had better biosecurity; Salmonella spp. were not found and Escherichia coli levels were substantially reduced (from 10(7) to 10(4) cfu/g). In summary, HWEM of superior quality can be produced when the processing conditions optimized in the current research are utilized.

  6. PERFORMANCE OF CEMENT MORTARS REPLACED BY GROUND WASTE BRICK IN DIFFERENT AGGRESSIVE CONDITIONS

    ILHAMI DEMIR

    2011-09-01

    Full Text Available This article investigates the sulphate resistance of cement mortars when subjected to different exposure conditions. Cement mortars were prepared using ground waste brick (GWB as a pozzolanic partial replacement for cement at replacement levels of 0%, 2.5%, 5%, 7.5, 10%, 12.5 and 15%. Mortar specimens were stored under three different conditions: continuous curing in lime-saturated tab water (TW, continuous exposure to 5% sodium sulphate solution (SS, and continuous exposure to 5% ammonium nitrate solution (AN, at a temperature of 20 ± 3 ºC, for 7, 28, 90, and 180 days. Prisms with dimensions of 25×25×285 mm, to determine the expansions of the mortar samples; and another set of prisms with dimensions of 40×40×160 mm, were prepared to calculate the compressive strength of the samples. It was determined that the GWB replacement ratios between 2.5% and 10% decreased the 180 days expansion values. The highest compressive strength values were found for the samples with 10% replacement ratio in the TW, SS, and AN conditions for 180 days. The microstructure of the mortars were investigated using scanning electron microscopy (SEM and the Energy dispersive X-ray (EDX.

  7. Ra-226 and Rn-222 in saline water compartments of the Aral Sea region

    Schettler, Georg; Oberhänsli, Hedi; Hahne, Knut

    2015-01-01

    Highlights: • 222 Rn and 226 Ra concentrations in different water compartments of the Aral Sea region. • 226 Ra-analysis based on 222 Rn-ingrowth versus MS-analysis after solid-phase extraction. • 226 Ra in different groundwater types of the Aral Sea Basin. • 222 Rn distribution in the Aral Sea, western basin. - Abstract: The Aral Sea has been shrinking since 1963 due to extensive irrigation and the corresponding decline in the river water inflow. Understanding of the current hydrological situation demands an improved understanding of the surface water/groundwater dynamics in the region. 222 Rn and 226 Ra measurements can be used to trace groundwater discharge into surface waters. Data of these radiometric parameters were not previously available for the study region. We determined 222 Rn activities after liquid phase extraction using Liquid Scintillation Counting (LSC) with peak-length discrimination and analyzed 226 Ra concentrations in different water compartments of the Amu Darya Delta (surface waters, unconfined groundwater, artesian water, and water profiles from the closed Large Aral Sea (western basin). The water samples comprise a salinity range between 1 and 263 g/l. The seasonal dynamics of solid/water interaction under an arid climate regime force the hydrochemical evolution of the unconfined groundwater in the Amu Darya Delta to high-salinity Na(Mg)Cl(SO 4 ) water types. The dissolved radium concentrations in the waters were mostly very low due to mineral over-saturation, extensive co-precipitation of radium and adsorption of radium on coexisting solid substrates. The analysis of very low 226 Ra concentrations (<10 ppq) at remote study sites is a challenge. We used the water samples to test and improve different analytical methods. In particular, we modified a procedure developed for the α-spectrometric determination of 226 Ra after solid phase extraction of radium using 3M Empore™ High Performance Extraction Disks (Purkl, 2002) for the analysis of the radionuclide using an ICP sector field mass spectrometer. The 226 Ra concentration of 17 unconfined groundwater samples ranged between 0.2 and 5 ppq, and that of 28 artesian waters between <0.2 and 13 ppq. The ICP-MS results conformed satisfactorily to analytical results based on γ-measurements of the 222 Rn ingrowth after purging and trapping on super-cooled charcoal. The 226 Ra concentrations were positively correlated with the salinity and the dissolved NaCl concentrations. The occurrence of unusually high 226 Ra activities is explained by radium release from adsorption sites with increasing salinity. The inferred spatial variability of 222 Rn in the Aral Sea and of 222 Rn and 226 Ra in the groundwater of the Amu Darya Delta is discussed in the context of our own previous hydrochemical studies in the study sites. Relatively low 222 Rn activities in the unconfined GW (1–9.5 Bq/l) indicate the alluvial sediments hosting the GW to be a low- 238 U( 226 Ra) substrate. Positive correlations between U and 226 Ra, and U and 222 Rn are likely related to locally deposited Fe(Mn)OOH precipitates. The 222 Rn activity of the GW, however, distinctly exceeds the 222 Rn concentration in the Aral Sea (10 mBq/l), in principle, making 222 Rn a sensitive tracer for the inflow of GW. The high water volume of the Large Aral Sea and wind induced mixing of its water body, however, hamper the detection of local groundwater inflow

  8. The effects of chronic, low doses of Ra-226 on cultured fish and human cells

    Shi, Xiaopei; Seymour, Colin; Mothersill, Carmel, E-mail: mothers@mcmaster.ca

    2016-07-15

    Purpose: To determine the chronic low-dose radiation effects caused by α-particle radiation from {sup 226}Ra over multiple cell generations in CHSE/F fish cells and HaCaT human cells. Methods: CHSE/F cells and HaCaT cells were cultured in medium containing {sup 226}Ra to deliver the chronic low-dose α-particle radiation. Clonogenic assay was used to test the clonogenic survival fractions of cells with or without being exposed to radiation from {sup 226}Ra. Results: The chronic low-dose radiation from {sup 226}Ra does have effects on the clonogenic survival of CHSE/F cells and HaCaT cells. When CHSE/F cells were cultured in {sup 226}Ra-medium over 9 passages for about 134 days, the clonogenic surviving fractions for cells irradiated at dose rates ranging from 0.00066 to 0.66 mGy/d were significantly lower than that of cells sham irradiated. For HaCaT cells grown in medium containing the same range of {sup 226}Ra activity, the clonogenic surviving fraction decreased at first and reached the lowest value at about 42 days (8 passages). After that, the clonogenic survival began to increase, and was significantly higher than that of control cells by the end of the experimental period. Conclusion: The chronic, low-dose high LET radiation from {sup 226}Ra can influence the clonogenic survival of irradiated cells. CHSE/F cells were sensitized by the radiation, and HaCaT cells were initially sensitized but later appeared to be adapted. The results could have implications for determining risk from chronic versus acute exposures to radium. - Highlights: • Cells were exposed to chronic low-dose α-radiation from {sup 226}Ra in medium with {sup 226}Ra. • The clonogenic survival of CHSE/F cells decreased when exposed to {sup 226}Ra for 134 days. • The clonogenic survival of HaCaT cells decreased at first and then increased. • The doubling time of both cells were not affected by this kind of radiation.

  9. Ra-226 collective dosimetry for surface waters in the uranium mining region of Pocos de Caldas

    Paschoa, A.S.; Sigaud, G.M.; Montenegro, E.C.; Baptista, G.B.

    1980-01-01

    Graphs of the collective dose equivalent for the whole body, bone, gastro-intestinal tract (lower large intestine), kidneys, and liver, via the pathways of drinking water and ingestion of food grown in irrigated fields are presented as a function of the 226 Ra concentrations in the surface waters of the Pocos de Caldas region. The collective dose equivalent calculated from the 226 Ra concentrations measured in the baseline studies are compared with those collective dose equivalent estimated from the projected higher 226 Ra concentrations in the river waters. The 226 Ra concentrations in river waters of the region are expected to be enhanced due to 226 Ra releases from uranium mining and milling operations. The dose equivalent commitment for the exposed population for the referred pathways is also estimated for the contribution of the mine during its predicted time of operation. The assumptions for the dose calculations are presented and the results obtained are discussed. (H.K.)

  10. Adopted levels and derived limits for Ra-226 and the decision making processes concerning TENORM releases

    Paschoa, A.S.

    2002-01-01

    A fraction of a primary dose limit can be, in general, agreed upon as a dose related level to be adopted in decision-making processes. In the case of TENORM releases, fractions of primary dose levels for 226 Ra, 228 Ra, and 210 Po may be of particular importance to establish adopted levels and derived limits to guide decision making processes. Thus, for example, a registration level for 226 Ra could be adopted at the highest portion of the natural background variation. Above such level, intervention and remedial action levels could also be adopted. All those levels would be fractions of the primary level, but translated in terms of derived limits expressed in practical units. Derived limits would then be calculated by using environmental models. In such approach 'critical groups' would have to be carefully defined and identified. In addition, the size of a critical group would be chosen to be used in environmental modeling. Site specific environmental models and parameters are desirable, though unavailable, or very difficult to obtain, in most cases. Thus, mathematical models and parameters of more generic nature are often used. A sensitive parametric analysis can make a ranking of the parameters used in a model, allowing one to choose how important each parameter will be for the model output. The paper will point out that when using the adopted levels and derived limits, as suggested above, the uncertainties and importance of the parameters entering an environmental model can make the difference for decision makers to take the right or wrong decision, as far as radiological protection is concerned. (author)

  11. Adopted levels and derived limits for Ra-226 and the decision making processes concerning TENORM releases

    Paschoa, A.S.

    2002-01-01

    A fraction of a primary dose limit can be, in general, agreed upon as a dose related level to be adopted in decision-making processes. In the case of TENORM releases, fractions of primary dose levels for 226 Ra, 228 Ra, and 210 Po may be of particular importance to establish adopted levels for 226 Ra could be adopted at the highest portion of the natural background variation. Above such level, intervention and remedial action levels could also be adopted. All those levels would be fractions of the primary level, but translated in terms of derived limits expressed in practical units. Derived limits would then be calculated by using environmental models. In such approach 'critical groups' would have to be carefully defined and identified. In addition, the size of a critical group would be chosen to be used in environmental modeling. Site specific environmental models and parameters are desirable, though unavailable, or very difficult to obtain, in most cases. Thus, mathematical models and parameters of more generic nature are often used. A sensitive parametric analysis can make a ranking of the parameters used in a model, allowing one to choose how important each parameter will be for the model output. The paper will point out that when using the adopted levels and derived limits, as suggested above, the uncertainties and importance of the parameters entering an environmental model can make the difference for decision makers to take the right or wrong decision, as far as radiological protection is concerned. (author)

  12. 40 CFR 261.5 - Special requirements for hazardous waste generated by conditionally exempt small quantity...

    2010-07-01

    ...(e). (2) A total of 100 kilograms of any residue or contaminated soil, waste, or other debris... accumulation, only in an on-site process subject to regulation under 40 CFR 261.6(c)(2); or (4) Is used oil... waste, so long as the hazardous waste that is treated was counted once; or (3) Spent materials that are...

  13. The effect of operating conditions on aquatic worms eating waste sludge

    Hendrickx, T.L.G.; Temmink, H.; Elissen, H.J.H.; Buisman, C.J.N.

    2009-01-01

    Several techniques are available for dealing with the waste sludge produced in biological waste water treatment. A biological approach uses aquatic worms to consume and partially digest the waste sludge. In our concept for a worm reactor, the worms (Lumbriculus variegatus) are immobilised in a

  14. Management responsible for the radioactive waste in the University of Costa Rica

    Mora, P.; Varela, A.

    2003-01-01

    Through the University Plan de Seguridad Radiologica (PSR), established in 1990, radioactive wastes generated by the University of Costa Rica (UCR) personnel are handled. They are properly collected, stroraged and disposed. The waste room is used by the following centers: Laboratorio de Fisica Nuclear Aplicada, Instituto de Investigaciones en Salud, Centro de Biologia Celular y Molecular and Centro de Investigaciones en Contaminacion Ambiental. The PSR has prestorage procedures, internal controls inside the waste room, protocols for storage, withdraw of sources, and discharges to the environment according to national and international legislation. The main radioactive wastes in liquid or solid forms contain p 32 , I 125 , S 35 y C 14 that eventually be disposed as excempted materials. The waste room stores sources with the following radionuclides Cs 137 , U 238 , Th 232 , Sr 90 , Ra 226 , Cd 109 , Cf 252 and Am 241 . It has 96 permanent sources and 52 that will be disposed. The PSR allows the University to have a centralized facility for the safe management of all radioactive waste generated locally. (Author) [es

  15. Action plan for response to abnormal conditions in Hanford high level radioactive liquid waste storage tanks containing flammable gases

    Sherwood, D.J.

    1994-03-01

    Radioactive liquid waste tends to produce hydrogen as a result of the interaction of gamma radiation and water. In tanks containing organic chelating agents, additional hydrogen gas as well as nitrous oxide and ammonia can be produced by thermal and radiolytic decomposition of these organics. Several high-level radioactive liquid waste storage tanks, located underground at the Hanford Site, contain waste that retains the gases produced in them until large quantities are released rapidly to the tank vapor space. Tanks filled to near capacity have relatively little vapor space; therefore, if the waste suddenly releases a large amount of hydrogen and nitrous oxide, a flammable gas mixture may result. The most notable waste tank with a flammable gas problem is tank 241-SY-101. Waste in this tank has occasionally released enough flammable gas to burn if an ignition source had been present inside of the tank. Several other waste tanks exhibit similar behavior to a lesser magnitude. Administrative controls have been developed to assure that these Flammable Gas Watch List tanks are safely maintained. Responses have also been developed for off-normal conditions which might develop in these tanks. In addition, scientific and engineering studies are underway to further understand and mitigate the behavior of the Flammable Gas Watch List tanks

  16. Environmental fate of Ra in cation-exchange regeneration brine waste disposed to septic tanks, New Jersey Coastal Plain, USA: migration to the water table.

    Szabo, Zoltan; Jacobsen, Eric; Kraemer, Thomas F; Parsa, Bahman

    2010-01-01

    Fate of radium (Ra) in liquid regeneration brine wastes from water softeners disposed to septic tanks in the New Jersey Coastal Plain was studied. Before treatment, combined Ra ((226)Ra plus (228)Ra) concentrations (maximum, 1.54 Bq L(-1)) exceeded the 0.185 Bq L(-1) Maximum Contaminant Level in 4 of 10 studied domestic-well waters (median pH, 4.90). At the water table downgradient from leachfields, combined Ra concentrations were low (commonly 5.3, indicating sequestration; when pH was septic-tank effluents (maximum, 0.243 Bq L(-1))), indicating Ra mobilization from leachfield sediments. Confidence in quantification of Ra mass balance was reduced by study design limitations, including synoptic sampling of effluents and ground waters, and large uncertainties associated with analytical methods. The trend of Ra mobilization in acidic environments does match observations from regional water-quality assessments.

  17. The Canadian development program for conditioning CANDU reactor wastes for disposal

    Charlesworth, D.H.; Bourns, W.T.; Buckley, L.P.

    1978-07-01

    Currently, radioactive wastes arising from the operation of Canadian nuclear reactors are placed in interim storage in concrete containment structures except for gaseous and liquid wastes containing small amounts of radioactivity which are dispersed. With the objective of replacing storage by permanent disposal, a program is underway to develop and demonstrate an integrated process for converting all reactor wastes to a stable, leach-resistant form which will immobilize the radionuclides in the waste repository. The major tool for this development is a Waste Treatment Centre, now being constructed at Chalk River Nuclear Laboratories, which will combine reverse-osmosis, incineration, evaporation and bituminizing processes. (author)

  18. Microbial ecology of Rum Jungle, III. Leaching behaviour of sulphidic waste material under controlled conditions

    Babij, T.; Goodman, A.; Khalid, A.M.; Ralph, B.J.

    1981-12-01

    The discharge, into river systems, of acid and heavy metals generated by leaching of sulphidic waste materials at the abandoned opencut uranium mine at Rum Jungle, Northern Territory, is causing continuing pollution of the surrounding environment. The maximum effects of acid and microorganisms on samples from the overburden dump material, under defined and controlled environmental conditions, were assessed using reactor systems. These samples came from the overburden dump resulting from the mining of White's orebody. Similarly, the stability of tailings material under conditions of flooding and increasing acidity was determined. At ph 2.5, metals in White's dump material were solubilised by acid attack only, whereas at pH 3.5, bacterial activity (principally that of Thiobacillus ferrooxidans) generated acidity and contributed significantly to metal release. Under microaerophilic conditions Thiobacillus ferrooxidans continued to effect metal release from the ore, but did not produce further acidity. If White's overburden is returned to the acidic, flooded opencuts, complete solubilisation of the material will occur. The exclusion of oxygen from the dump will not necessarily stop bacterially catalysed leaching processes. Under highly aerated and agitated flooded conditions the tailings material was not active, except for copper release of about 2 g kg -1 ore at pH 4.0. The only deleterious element released by increasing acidity was copper, which was 100 per cent solubilised at pH 2.5. Uranium was always lss than 3 μg kg -1 ore, and lead was detected only at pH 2.5. Indigenous leaching bacteria did not develop

  19. Preoperational Subsurface Conditions at the Idaho Nuclear Technology and Engineering Center Service Waste Disposal Facility

    Ansley, Shannon Leigh

    2002-02-01

    The Idaho Nuclear Technology and Engineering Center (INTEC) Service Wastewater Discharge Facility replaces the existing percolation ponds as a disposal facility for the INTEC Service Waste Stream. A preferred alternative for helping decrease water content in the subsurface near INTEC, closure of the existing ponds is required by the INTEC Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Record of Decision (ROD) for Waste Area Group 3 Operable Unit 3-13 (DOE-ID 1999a). By August 2002, the replacement facility was constructed approximately 2 miles southwest of INTEC, near the Big Lost River channel. Because groundwater beneath the Idaho National Engineering and Environmental Laboratory (INEEL) is protected under Federal and State of Idaho regulations from degradation due to INEEL activities, preoperational data required by U.S. Department of Energy (DOE) Order 5400.1 were collected. These data include preexisting physical, chemical, and biological conditions that could be affected by the discharge; background levels of radioactive and chemical components; pertinent environmental and ecological parameters; and potential pathways for human exposure or environmental impact. This document presents specific data collected in support of DOE Order 5400.1, including: four quarters of groundwater sampling and analysis of chemical and radiological parameters; general facility description; site specific geology, stratigraphy, soils, and hydrology; perched water discussions; and general regulatory requirements. However, in order to avoid duplication of previous information, the reader is directed to other referenced publications for more detailed information. Documents that are not readily available are compiled in this publication as appendices. These documents include well and borehole completion reports, a perched water evaluation letter report, the draft INEEL Wellhead Protection Program Plan, and the Environmental Checklist.

  20. Selection of hydrothermal pre-treatment conditions of waste sludge destruction using multicriteria decision-making.

    Al-Shiekh Khalil, Wael; Shanableh, Abdullah; Rigby, Portia; Kokot, Serge

    2005-04-01

    The effectiveness of hydrothermal treatment for the destruction of the organic content of sludge waste was investigated. The sludge sampled in this study contained approximately 2% solids. The experimental program consisted of hydrothermal treatment experiments conducted in a batch reactor at temperatures between 100 and 250 degrees C, with the addition of an oxidant (hydrogen peroxide) in the range of 0-150% with reference to TCOD, and reaction times of up to 60 min. The results suggested that the availability of oxidant, reaction temperature and reaction time were the determining factors for COD removal. A significant fraction of the COD remaining after treatment consisted of the dissolved COD. The results confirmed that hydrothermal treatment proceeds through hydrolysis resulting in the production of dissolved organic products followed by COD removal through oxidation. Two MCDM chemometrics methods, PROMETHEE and GAIA, were applied to process the large data matrix so as to facilitate the selection of the most suitable hydrothermal conditions for sludge destruction. Two possible scenarios were produced from this analysis-one depended on the use of high temperatures and no oxidant, while the second offered a choice of compromise solutions at lower temperatures but with the use of at least some oxidant. Thus, for the final choice of operating conditions, the decision maker needs local knowledge of the costs and available infrastructure. In principle, such information could be added as further criteria to the data matrix and new rankings obtained.

  1. Wastes

    Bovard, Pierre

    The origin of the wastes (power stations, reprocessing, fission products) is determined and the control ensuring the innocuity with respect to man, public acceptance, availability, economics and cost are examined [fr

  2. Conditioning experience for spent radium sources

    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

  3. A hydrothermal flow-through apparatus to simulate leaching of nuclear waste forms under quasi-dynamic conditions

    Heimann, R.B.

    1985-03-01

    A hydrothermal flow-through apparatus has been designed that will allow the testing of individual waste package components, as well as combinations of these, under a wide range of environmental conditions. The maximum permissible temperature is 700 degrees C, while the maximum pressure is 300 MPa. Flow rates can be adjusted by sequential operation of a pneumatically operated valve with preset pause and working cycles. The main applications of the apparatus to nuclear fuel waste management research are: (i) the study of migration of ionic species through a rock column at specified hydraulic head, and (ii) the study of the rate of leaching of radionuclides from waste forms under disposal vault conditions in the presence of groundwater with variable flow rates

  4. KONTEC 2009. Report about the 9th International Symposium on ''Conditioning of radioactive operational and decommissioning wastes''

    Anon.

    2009-01-01

    ''Kontec 2009'' was organized in Dresden on April 15-17, 2009. For the 8 th time, this established international meeting covered the subjects of ''Conditioning of Radioactive Operational and Decommissioning Wastes'' and ''Decommissioning and Dismantling of Nuclear Facilities'' and the R and D Status Report delivered by the German Federal Ministry for Education and Research on this key topic. Some 790 participants from 13 countries heard and discussed the contributions to the three-day meeting. The program of the symposium comprised plenary sessions dealing with these 4 key subjects: Disposal of Radioactive Residues from Nuclear Facilities' Operation and Decommissioning, Decommissioning and Dismantling of Nuclear Facilities, Facilities and Systems for the Conditioning of Operational and Decommissioning Wastes, Transport, Interim and Final Storage of Non-heat Generating Wastes (i.e. Konrad). The sessions were supplemented by poster sessions and selected short presentations under the heading of ''Kontec Direct.'' (orig.)

  5. Feasibility study of using agriculture waste as desiccant for air conditioning system

    Khedari, J.; Rawangkul, R.; Hirunlabh, J. [King Mongkut' s University of Technology Thonburi, Bangkok (Thailand). Buidling Scientific Research Center; Chimchavee, W. [University of Thai Chamber of Commerce, Bangkok (Thailand); Watanasungsuit, A. [South East Asia Univ., Bangkok (Thailand). Engineering Management

    2003-08-01

    This research was aimed at investigating the feasibility of using dried agricultural waste as desiccant for an open cycle air conditioning system. The natural fibers are, therefore, intended to replace chemical desiccant such as silica gel, molecular sieves etc. The investigation was limited to Coconut coir (Cocos nucifera) and Durian peels (Durio zibethinus). Experimental results confirmed that dry coconut coir and durian peel can absorb 30 g and 17 g H{sub 2}O per 100 g dry product, respectively, from air at the average condition of 32{sup o}C and 75% relative humidity. The optimum airflow rate is about 84 and 98 m{sup 3}/hr-100 g dry product, respectively. Therefore, the dry coconut coir is more suitable than the dry durian peel. Comparison between the dry coconut coir and silica gel showed that the average adsorption rate of coconut coir is less than that of silica gel by about 5 g/h-100 g dry product at an airflow rate of 84 m{sup 3}/h and 60 min operating time. However, it is still an interesting option to replace silica gel in open cycle air conditioning system, as the decrease of average adsorption rate is rather small. The other extremely interesting advantage of coconut coir is that during moisture absorption the heat generated during the process is less important. That means the air leaves the coconut coir bed at a lower temperature compared to that with a silica gel. Therefore, the saving of cooling energy is much more important. (Author)

  6. Microbial gas generation under expected Waste Isolation Pilot Plant repository conditions

    Francis, A.J.; Gillow, J.B.; Giles, M.R. [Brookhaven National Lab., Upton, NY (United States). Dept. of Applied Science

    1997-03-01

    Gas generation from the microbial degradation of the organic constituents of transuranic waste under conditions expected at the Waste Isolation Pilot Plant (WIPP) repository was investigated at Brookhaven National Laboratory. The biodegradation of mixed cellulosics (various types of paper) and electron-beam irradiated plastic and rubber materials (polyethylene, polyvinylchloride, neoprene, hypalon, and leaded hypalon) was examined. The rate of gas production from cellulose biodegradation in inundated samples incubated for 1,228 days at 30 C was biphasic, with an initial rapid rate up to approximately 600 days incubation, followed by a slower rate. The rate of total gas production in anaerobic samples containing mixed inoculum was as follows: 0.002 mL/g cellulose/day without nutrients; 0.004 mL/g cellulose/day with nutrients; and 0.01 mL/g cellulose/day in the presence of excess nitrate. Carbon dioxide production proceeded at a rate of 0.009 {micro}mol/g cellulose/day in anaerobic samples without nutrients, 0.05 {micro}mol/g cellulose/day in the presence of nutrients, and 0.2 {micro}mol/g cellulose/day with excess nitrate. Adding nutrients and excess nitrate stimulated denitrification, as evidenced by the accumulation of N{sub 2}O in the headspace (200 {micro}mol/g cellulose). The addition of the potential backfill bentonite increased the rate of CO{sub 2} production to 0.3 {micro}mol/g cellulose/day in anaerobic samples with excess nitrate. Analysis of the solution showed that lactic, acetic, propionic, butyric, and valeric acids were produced due to cellulose degradation. Samples incubated under anaerobic humid conditions for 415 days produced CO{sub 2} at a rate of 0.2 {micro}mol/g cellulose/day in the absence of nutrients, and 1 {micro}mol/g cellulose/day in the presence of bentonite and nutrients. There was no evidence of biodegradation of electron-beam irradiated plastic and rubber.

  7. Treatment Conditions of Building Wastes in China and Its Integrated Management Measures

    Liu Dan; Zha Kun; Li Qibin

    2006-01-01

    The status of utilization and disposal of the building wastes are introduced on the basis of analysis of its compositions, generation and effects on urban environment. The basic framework of the integrated building waste management, including control of the sources, reduction of the integrated process and final disposal, are proposed in view of the problems existing in recovery of the building wastes and the experiences from the developed countries.

  8. The role of equilibrium leach testing in understanding the behaviour of nuclear wastes under disposal conditions

    Biddle, P.; Rees, J.H.

    1988-01-01

    Results from the equilibrium leach testing of a range of intermediate level nuclear wastes have been modelled using sorption and solubility data obtained in experiments with individual radionuclides. The wastes involved were AGR hulls, Magnox cladding wastes, combustible plutonium-contaminated materials and ferric/aluminium hydroxide flocs. The test has an important role in validating near-field models, and helps to build confidence in disposal assessments. (author)

  9. Responsible handling of the radioactive waste at the Universidad de Costa Rica

    Mora Rodriguez, Patricia; Varela, Alfonso

    2006-01-01

    The Radiation Safety Program (RSP) of the Universidad de Costa Rica established in 1990, handles the radioactive waste generated at the University. A centralized storage waste room is used by the Centro de Investigacion en Ciencias Atomicas, Nucleares y Moleculares, Instituto de Investigacion en Salud, Centro de Investigacion en Biologia Celular y Molecular, and the Centro de Investigacion en Contaminacion Ambiental. The RSP has pre-storage procedures, internal controls, protocols for storage, withdrawal of sources and discharges to the environment, according to national and international legislation. The main radionuclides in liquid and solid wastes are P32, I125, S35 y C14; which after a storage period will be disposed of as exempted materials. The waste room also permanently stores sources with the following radionuclides Cs137, U238, Th232, Sr90, Ra226, Cd109, Cf252 and Am241. It has 96 permanent sources and 52 that will be disposed of. The RSP allows the University to have a centralized facility for the safe management of all radioactive waste generated locally. (Author)

  10. Conditioning technology of spent radium sources

    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

  11. The influence of waste treatment, conditioning and packaging on design for disposal

    Tufton, E.P.S.; Whipp, H.G.; Putte, D.V.

    1990-01-01

    The design of a repository for low and intermediate level waste will always have a number of targets; safety, capacity, cost and ease of operation being prominent. Achieving the targets requires a total design of the waste management system, which ranges from treatment of the raw waste form at the source of arising to design for post-closure performance of the repository. In working on repository designs and their safety assessments, the authors have found that different waste forms have significant influences on the repository and this paper is concerned with those influences. 1 ref

  12. Proposal of conditioning of the not-in-use sealed sources which are stored in the Radioactive Wastes Treatment Facility

    Jova, L.; Garcia, N.; Benitez, J.C.; Salgado, M.; Hernandez, A.

    1996-01-01

    There is a considerable number of sealed sources which are no longer in use at the radioactive wastes treatment facility. In the present work a methodology is proposed for the final conditioning of these sources, based on their immobilization in a cement matrix. This cementation is accomplished within a 200-liter tank

  13. Two-step upflow anaerobic sludge bed system for sewage treatment under subtropical conditions with posttreatment in waste stabilization ponds

    Seghezzo, L.; Trupiano, A.P.; Liberal, V.; Todd, P.G.; Figueroa, M.E.; Gutierrez, M.A.; Silva Wilches, Da A.C.; Iribarnegaray, M.; Guerra, R.G.; Arena, A.; Cuevas, C.M.; Zeeman, G.; Lettinga, G.

    2003-01-01

    A pilot-scale sewage treatment system consisting of two upflow anaerobic sludge bed (UASB) reactors followed by five waste stabilization ponds (WSPs) in series was studied under subtropical conditions. The first UASB reactor started up in only 1 mo (stable operation, high chemical oxygen demand

  14. An estimate of conditioned waste arisings to the years 2000 and 2010 for the Department of Energy power generation scenarios

    Fairclough, M.P.; Moore, D.C.; Tymons, B.J.

    1984-09-01

    An estimate of conditioned waste arisings to the years 2000 and 2010 has been made using evidence presented at the Sizewell 'B' public enquiry. The method of calculation has been based on the rate of arisings per GWe year and the power programmes of the Department of Energy. (author)

  15. Effects of prevailing conditions during second Palestinian uprising on solid waste management system in Nablus city in Palestine.

    Arafat, Hassan A; Al-Khatib, Issam A; Zahra, Abdulsalam Abu

    2006-08-01

    Since the start of the second Palestinian uprising (Al-Aqsa Intifada), and due to the Israeli activities, curfews, closures, and military checkpoints imposed since 2000, the quality of social services rendered by Nablus city has been gradually deteriorating. Solid waste management in Nablus city was badly affected by these conditions, and this situation is negatively affecting health and damaging the environment. Most of these cases were due to reasons beyond the capability of the municipality with its limited resources. This study revealed that some of the important municipal solid waste (MSW) equipment had been damaged during the uprising. The workforce in the MSW system was reduced and certain MSW-related development projects and activities have been frozen due to the current conditions. The city's medical waste incinerator had been phased out and the number of special medical containers had been reduced from 16 to 10. Some MSW compressing trucks had been out of use with no substitute. Another important figure is the number of waste collection workers which decreased from 420 to 301, although the city is growing in premises as well as population. The created unsanitary solid waste transfer station is now a pollution source on its own, causing an ugly scene at the eastern entrance of Nablus city. There should be a comprehensive and urgent solution for this problem and the needed resources should be invested.

  16. Behavior of ruthenium, cesium and antimony in high temperature processes for waste conditioning

    Klein, M.; Weyers, C.; Goossens, W.R.A.

    1985-01-01

    The fission products and the actinides of high level radioactive liquid wastes can be immobilized by incorporation into a glass matrix prior to disposal. The behaviour of so-called semi-volatile products during the vitrification process has been studied by the C.E.N./S.C.K. in Mol since 1979 in the framework of a contract with DWK of Germany in support to the HAW technological program PAMELA. The experiments were performed on laboratory and semi-pilot scale using simulated LEWC solutions tagged with radioisotopes of three suspected volatile fission products, namely ruthenium, cesium and antimony. The releases of these semi-volatile compounds to the off-gases have been investigated for a liquid fed melter as a function of the operational conditions. The study of a wet purification system, comprising in series of a dust scrubber, a condensor, an ejector venturi and an NOsub(x) column, has shown that cesium appears to be the reference isotope for the volatile elements released from the melter. Ruthenium seems not to be a problem from the point of view of gas purification although local radiation problems caused by deposits on metal surfaces cannot be excluded. (Auth.)

  17. Preliminary results from uranium/americium affinity studies under experimental conditions for cesium removal from NPP ''Kozloduy'' simulated wastes solutions

    Nikiforova, A.; Kinova, L.; Peneva, C.; Taskaeva, I.; Petrova, P.

    2005-01-01

    We use the approach described by Westinghouse Savannah River Company using ammonium molybdophosphate (AMP) to remove elevated concentrations of radioactive cesium to facilitate handling waste samples from NPP K ozloduy . Preliminary series of tests were carried out to determine the exact conditions for sufficient cesium removal from five simulated waste solutions with concentrations of compounds, whose complexing power complicates any subsequent processing. Simulated wastes solutions contain high concentrations of nitrates, borates, H 2 C 2 O 4 , ethylenediaminetetraacetate (EDTA) and Citric acid, according to the composition of the real waste from the NPP. On this basis a laboratory treatment protocol was created. This experiment is a preparation for the analysis of real waste samples. In this sense the results are preliminary. Unwanted removal of non-cesium radioactive species from simulated waste solutions was studied with gamma spectrometry with the aim to find a compromise between on the one hand the AMP effectiveness and on the other hand unwanted affinity to AMP of Uranium and Americium. Success for the treatment protocol is defined by proving minimal uptake of U and Am, while at the same time demonstrating good removal effectiveness through the use of AMP. Uptake of U and Am were determined as influenced by oxidizing agents at nitric acid concentrations, proposed by Savannah River National laboratory. It was found that AMP does not significantly remove U and Am when concentration of oxidizing agents is more than 0.1M for simulated waste solutions and for contact times inherent in laboratory treatment protocol. Uranium and Americium affinity under experimental conditions for cesium removal were evaluated from gamma spectrometric data. Results are given for the model experiment and an approach for the real waste analysis is chosen. Under our experimental conditions simulated wastes solutions showed minimal affinity to AMP when U and Am are most probably in

  18. The influence of mineral additives on the mechanical performances of the conditioning matrix of radioactive waste by cementation

    Dragolici, F.; Rotarescu, G.; Turcanu, C.N.

    1997-01-01

    To improve the quality of the conditioning matrix of radioactive waste by the cementation technology, mineral additives which are diminishing the leaching rate of the radionuclides in the disposal environment are used. The studies performed until now have as an objective the obtaining of the most propitious mixture of cement and bentonite or cement and volcanic tuff, which have the mechanical properties similar to the cement paste used for the conditioning of the radioactive waste. This mixture, cement - mineral binder, in the future is required to be used at the Radioactive Waste Treatment Plant - IPNE - HH Bucharest- Magurele for the conditioning of the radioactive wastes, taking in consideration the properties of these mineral binders: very good plasticity and capacity of adsorption, which lead at the decrease of porosity. Bentonite is a clay already used in the technology of disposal as a filling material to diminish the radioactive spreading because of degradation in time of the metallic package or the intrusion of casual water. The composition of the cement - bentonite - water system is checked by the cement to water and cement to bentonite ratio, by strength and by the separated water volume. The studies show that the best mechanical performance was obtained for a cement to water ratio 10. Taking in consideration the property of bentonite to fill compactly the free spaces in the presence of water, what entails the occurrence of internal tensions in the matrix structure, which leads, in turn, to appearance of microfissures, the mixtures examined by mechanical tests had in their composition less than 10 % bentonite. For volcanic tuff, similar results were obtained using almost the same ratios. In these conditions, the results obtained allow to draw the conclusion that the adequate usage of the mineral additives do not change the resistance of the cement paste used in the conditioning of the radioactive waste. (authors)

  19. An industry perspective on commercial radioactive waste disposal conditions and trends.

    Romano, Stephen A

    2006-11-01

    The United States is presently served by Class-A, -B and -C low-level radioactive waste and naturally-occurring and accelerator-produced radioactive material disposal sites in Washington and South Carolina; a Class-A and mixed waste disposal site in Utah that also accepts naturally-occurring radioactive material; and hazardous and solid waste facilities and uranium mill tailings sites that accept certain radioactive materials on a site-specific basis. The Washington site only accepts low-level radioactive waste from 11 western states due to interstate Compact restrictions on waste importation. The South Carolina site will be subject to geographic service area restrictions beginning 1 July 2008, after which only three states will have continued access. The Utah site dominates the commercial Class-A and mixed waste disposal market due to generally lower state fees than apply in South Carolina. To expand existing commercial services, an existing hazardous waste site in western Texas is seeking a Class-A, -B and -C and mixed waste disposal license. With that exception, no new Compact facilities are proposed. This fluid, uncertain situation has inspired national level rulemaking initiatives and policy studies, as well as alternative disposal practices for certain low-activity materials.

  20. Examining the role of canister cooling conditions on the formation of nepheline from nuclear waste glasses

    Christian, J. H. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2015-09-01

    Nepheline (NaAlSiO₄) crystals can form during slow cooling of high-level waste (HLW) glass after it has been poured into a waste canister. Formation of these crystals can adversely affect the chemical durability of the glass. The tendency for nepheline crystallization to form in a HLW glass increases with increasing concentrations of Al₂O₃ and Na₂O.

  1. Thermoluminescence response of calcic bentonite subjected to conditions of high nuclear waste underground storage

    Dies, J.; Miralles, L.; Tarrasa, F.; Pueyo, J.J.; Cuevas, C. de las

    2002-01-01

    Bentonite is regarded as a backfilling material for underground storage facilities of highly radioactive nuclear waste built on granite formations. In these facilities, bentonite will be subjected to a gradient of temperature and dose rate, achieving a very high integrated dose and, therefore, changes in its structure and physical properties may take place. Two experiments to discriminate between the thermal and the irradiation effect were performed. In the first (named BIC-2A), samples were subjected to temperature while in second (named BIC-2B) the combined effect of temperature and irradiation was studied. The experimental conditions were: a thermal gradient between 130 deg. C and 90 deg. C, a maximum dose rate of 3.5 kGy.h -1 and a gradient of the integrated dose between 1.75 MGy and 10 MGy. Both experiments lasted a total of 124 days. An irradiation source of 60 Co with an activity close to 300,000 Ci, and bentonite samples of 200 mm in length and 50 mm in diameter were used. After the experiment, the samples were ground and two fractions were obtained: a fine fraction ( 80 μm). The results are described of thermoluminescence analyses on the two fractions obtained which showed that the coarse fractions can be 100 times more sensitive to radiation than the fine fraction. On the other hand, the heated and irradiated samples showed a thermoluminescence response around 50 times greater than the samples that were only heated. In addition to this, the temperature and dose rate conditions are relevant parameters in the generation and stabilisation of radiation induced defects. Finally, the response of samples heated and irradiated for two months was quite similar to that obtained on samples heated and irradiated for four months, indicating a saturation phenomenon. (author)

  2. Chemical profiling of Jatropha tissues under different torrefaction conditions: application to biomass waste recovery.

    Taiji Watanabe

    Full Text Available Gradual depletion of the world petroleum reserves and the impact of environmental pollution highlight the importance of developing alternative energy resources such as plant biomass. To address these issues, intensive research has focused on the plant Jatropha curcas, which serves as a rich source of biodiesel because of its high seed oil content. However, producing biodiesel from Jatropha generates large amounts of biomass waste that are difficult to use. Therefore, the objective of our research was to analyze the effects of different conditions of torrefaction on Jatropha biomass. Six different types of Jatropha tissues (seed coat, kernel, stem, xylem, bark, and leaf were torrefied at four different temperature conditions (200°C, 250°C, 300°C, and 350°C, and changes in the metabolite composition of the torrefied products were determined by Fourier transform-infrared spectroscopy and nuclear magnetic resonance analyses. Cellulose was gradually converted to oligosaccharides in the temperature range of 200°C-300°C and completely degraded at 350°C. Hemicellulose residues showed different degradation patterns depending on the tissue, whereas glucuronoxylan efficiently decomposed between 300°C and 350°C. Heat-induced depolymerization of starch to maltodextrin started between 200°C and 250°C, and oligomer sugar structure degradation occurred at higher temperatures. Lignin degraded at each temperature, e.g., syringyl (S degraded at lower temperatures than guaiacyl (G. Finally, the toxic compound phorbol ester degraded gradually starting at 235°C and efficiently just below 300°C. These results suggest that torrefaction is a feasible treatment for further processing of residual biomass to biorefinery stock or fertilizer.

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

    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.

  4. Recycling of radioactive oil sludge waste into pavement brick

    Meor Yusoff Meor Sulaiman; Hishamuddin Hussein; Choo Thye Foo; Nurul Wahida Ahmad Khairuddin; MAsliana MUslimin; Wilfred Sylvester Paulus

    2010-01-01

    Malaysia produces about 1450 tons of radioactive oil sludge waste per year and there is an urgent need to find a permanent solution to the storage and disposal of this radioactive waste problem. Several treatment methods such bacteria farming, ultracentrifuge, steam reforming and incineration are currently being used but the core issue of the radioactive material in the oil sludge had not been solved. The paper relates a study on utilizing the radioactive component of the oil sludge and turning them into pavement brick. Characteristic study of this radioactive component by XRD and XRF show that it mainly comprised of quartz and anorthite minerals. While the radioactivity analysis by gamma technique shows that more than 90 % of this radioactivity comes from this soil component with Ra-226 and Ra-228 as the main radionuclides. A vitrified brick was then produced from this sediment by mixing it with low radioactive local red clay. The result also shows that the formation of the vitrified layer may be due high content of K in the red clay. Tensile test on the brick shows that it has more than four times the strength of commercial clay brick. Long duration leaching test on the brick also shows that there is no dissolution of radionuclide from the brick. (author)

  5. Radioactive Waste Conditioning, Immobilisation, And Encapsulation Processes And Technologies: Overview And Advances (Chapter 7)

    Jantzen, Carol M. [Savannah River National Lab., Aiken SC (United States); Lee, William E. [Imperial College, London (United Kingdom). Dept. of Materials; Ojovan, Michael I. [Univ. of Sheffield (United Kingdom). Dept. of Materials Science and Engineering

    2012-10-19

    The main immobilization technologies that are available commercially and have been demonstrated to be viable are cementation, bituminization, and vitrification. Vitrification is currently the most widely used technology for the treatment of high level radioactive wastes (HLW) throughout the world. Most of the nations that have generated HLW are immobilizing in either alkali borosilicate glass or alkali aluminophosphate glass. The exact compositions of nuclear waste glasses are tailored for easy preparation and melting, avoidance of glass-in-glass phase separation, avoidance of uncontrolled crystallization, and acceptable chemical durability, e.g., leach resistance. Glass has also been used to stabilize a variety of low level wastes (LLW) and mixed (radioactive and hazardous) low level wastes (MLLW) from other sources such as fuel rod cladding/decladding processes, chemical separations, radioactive sources, radioactive mill tailings, contaminated soils, medical research applications, and other commercial processes. The sources of radioactive waste generation are captured in other chapters in this book regarding the individual practices in various countries (legacy wastes, currently generated wastes, and future waste generation). Future waste generation is primarily driven by interest in sources of clean energy and this has led to an increased interest in advanced nuclear power production. The development of advanced wasteforms is a necessary component of the new nuclear power plant (NPP) flowsheets. Therefore, advanced nuclear wasteforms are being designed for robust disposal strategies. A brief summary is given of existing and advanced wasteforms: glass, glass-ceramics, glass composite materials (GCM’s), and crystalline ceramic (mineral) wasteforms that chemically incorporate radionuclides and hazardous species atomically in their structure. Cementitious, geopolymer, bitumen, and other encapsulant wasteforms and composites that atomically bond and encapsulate

  6. Evaluation of storage and disposal costs for conditioned radioactive waste in several European countries

    Zaccai, H.

    1990-01-01

    A survey on radioactive waste storage and disposal costs has been performed. In order to proceed to such a cost assessment, a survey has been carried on within various nuclear waste agencies throughout Europe. In addition, in order to collect sufficient related economic data, reference has been made to other available information. The results may be summarized as follows: until disposal sites become available, many countries store low-level waste at costs between 400 and 1 400 ECU/m 3 ; little information is supplied for medium- and high-level waste storage; however, for the projects under way, levels of the order of 100 000 ECU/m 3 for vitrified waste are probable, whereas for medium- and high-level waste these costs are expected to vary from 10 000 to 20 000 ECU/m 3 ; the economic analysis of disposal facilities shows that cost elasticity is high at low capacities both for the surface disposal ( 3 ) and deep burial ( 3 ). The economic benefit that might result from the scaling effect at larger capacities appears to be of little significance; despite the diversity of geological formations and disposal concepts for which economic data were compared, a certain coherence can be detected; thus, for the disposal of low-level waste, costs evolve as a function of site capacity from 2 000 to 6 000 ECU/m 3 for deep burial, and from 1 000 to 3 000 ECU/m 3 for surface disposal or shallow burial. For deep burial of medium- and high-level waste, costs vary as a function of site capacity from 10 000 to 70 000 ECU/m 3 for non-heat-emitting waste, and from 0.4 to 1.4 MECU/m 3 for vitrified waste

  7. Minerals and design of new waste forms for conditioning nuclear waste; Les mineraux et la formulation de nouvelles matrices de stockage pour les dechets radioactifs

    Montel, J.M. [G2R, CNRS, Ecole nationale superieure de geologie, Nancy-universite, BP 70239, 54056 Vandoeuvre-les-Nancy (France)

    2011-02-15

    Safe storage of radioactive waste is a major challenge for the nuclear industry. Mineralogy is a good basis for designing ceramics, which could eventually replace nuclear glasses. This requires a new storage concept: separation-conditioning. Basic rules of crystal chemistry allow one to select the most suitable structures and natural occurrences allow assessing the long-term performance of ceramics in a geological environment. Three criteria are of special interest: compatibility with geological environment, resistance to natural fluids, and effects of self-irradiation. If mineralogical information is efficient for predicting the behaviour of common, well-known minerals, such as zircon, monazite or apatite, more research is needed to rationalize the long-term behaviour of uncommon waste form analogs. (author)

  8. Soil radium, soil gas radon and indoor radon empirical relationships to assist in post-closure impact assessment related to near-surface radioactive waste disposal.

    Appleton, J D; Cave, M R; Miles, J C H; Sumerling, T J

    2011-03-01

    Least squares (LS), Theil's (TS) and weighted total least squares (WTLS) regression analysis methods are used to develop empirical relationships between radium in the ground, radon in soil and radon in dwellings to assist in the post-closure assessment of indoor radon related to near-surface radioactive waste disposal at the Low Level Waste Repository in England. The data sets used are (i) estimated ²²⁶Ra in the < 2 mm fraction of topsoils (eRa226) derived from equivalent uranium (eU) from airborne gamma spectrometry data, (ii) eRa226 derived from measurements of uranium in soil geochemical samples, (iii) soil gas radon and (iv) indoor radon data. For models comparing indoor radon and (i) eRa226 derived from airborne eU data and (ii) soil gas radon data, some of the geological groupings have significant slopes. For these groupings there is reasonable agreement in slope and intercept between the three regression analysis methods (LS, TS and WTLS). Relationships between radon in dwellings and radium in the ground or radon in soil differ depending on the characteristics of the underlying geological units, with more permeable units having steeper slopes and higher indoor radon concentrations for a given radium or soil gas radon concentration in the ground. The regression models comparing indoor radon with soil gas radon have intercepts close to 5 Bq m⁻³ whilst the intercepts for those comparing indoor radon with eRa226 from airborne eU vary from about 20 Bq m⁻³ for a moderately permeable geological unit to about 40 Bq m⁻³ for highly permeable limestone, implying unrealistically high contributions to indoor radon from sources other than the ground. An intercept value of 5 Bq m⁻³ is assumed as an appropriate mean value for the UK for sources of indoor radon other than radon from the ground, based on examination of UK data. Comparison with published data used to derive an average indoor radon: soil ²²⁶Ra ratio shows that whereas the published data are

  9. Treatment, conditioning and packaging for final disposal of low and intermediate level waste from Cernavoda: a techno-economic assessment

    Suryanarayan, S.; Husain, A. [Kinectrics Inc., Toronto, ON (Canada); Fellingham, L.; Nesbitt, V. [Nuvia Ltd., Didcot, Oxfordshire (United Kingdom); Toro, L. [Mate-fin, Bucharest (Romania); Simionov, V.; Dumitrescu, D. [Cernavoda Nuclear Power Plant, Cernavoda (Romania)

    2011-07-01

    National Nuclearelectrica Society (SNN) owns and operates two CANDU-6 plants at Cernavoda in Romania. Two additional units are expected to be built on the site in the future. Low and intermediate level short-lived radioactive wastes from Cernavoda are planned to be disposed off in a near-surface repository to be built at Saligny. The principal waste streams are IX resins, filters, compactable wastes, non-compactables, organic liquids and oil-solid mixtures. Their volumetric generation rates per reactor unit are estimated to be: IX resins (6 m{sup 3}/y), filters (2 m{sup 3}/y), compactables (23 m{sup 3}/y) and non-compactables (15 m{sup 3}/y). A techno-economic assessment of the available options for a facility to treat and condition Cernavoda's wastes for disposal was carried out in 2009 based on projected waste volumes from all four units. A large number of processes were first screened to identify viable options. They were further considered to develop overall processing options for each waste stream. These were then consolidated to obtain options for the entire plant by minimizing the number of unit operations required to process the various waste streams. A total of 9 plant options were developed for which detailed costing was undertaken. Based on a techno-economic assessment, two top ranking plant options were identified. Several scenarios were considered for implementing these options. Amongst them, a contractor run operation of a facility located on the Cernavoda site was considered to be more cost effective than operating the facility using SNN personnel. (author)

  10. An initial study of the behaviour under repository conditions of inactive components of nuclear wastes

    Biddle, P.; Rees, J.H.

    1988-02-01

    This review extends the appreciation of repository behaviour to include the inactive components of wastes and their degradation products. These materials include a wide range of metals and organics, sludges and decommissioning wastes. The effect of degradation products on the solubility of long-lived radionuclides and any active daughters and their sorption on surfaces of the repository are assessed. Research requirements are identified that may help to improve significantly the assessment of the effects of inactive materials. Data required to improve the quality of inventory data on nuclear wastes are listed. (author)

  11. Siting process for disposal site of low level radiactive waste in Thailand

    Yamkate, P.; Sriyotha, P.; Thiengtrongjit, S.; Sriyotha, K.

    1992-01-01

    The radioactive waste in Thailand is composed of low level waste from the application of radioisotopes in medical treatment and industry, the operation of the 2 MW TRIGA Mark III Research Reactor and the production of radioisotopes at OAEP. In addition, the high activity of sealed radiation sources i.e. Cs-137 Co-60 and Ra-226 are also accumulated. Since the volume of treated waste has been gradually increased, the general needs for a repository become apparent. The near surface disposal method has been chosen for this aspect. The feasibility study on the underground disposal site has been done since 1982. The site selection criteria have been established, consisting of the rejection criteria, the technical performance criteria and the economic criteria. About 50 locations have been picked for consideration and 5 candidate sites have been selected and subsequent investigated. After thoroughly investigation, a definite location in Ratchburi Province, about 180 kilometers southwest of Bangkok, has been selected as the most suitable place for the near surface disposal of radioactive waste in Thailand

  12. Anaerobic corrosion of carbon steel under unsaturated conditions in a nuclear waste deep geological repository

    Kwong, G.; Wang, St.; Newman, R.C.

    2009-01-01

    Full text of publication follows: Anaerobic corrosion behaviour of carbon steel in humid conditions, but not submerged in aqueous solution, was studied based on hydrogen generation. Initial tests monitored the hydrogen evolution from carbon steel in a high humidity environment (≥ 75% RH) at near-ambient temperature (30 C) using a high sensitivity pressure gauge system (sensitivity of 0.01 μm.a -1 ). The presence of hydrogen in test runs that showed no, or minimal, pressure increase was confirmed by a solid-state potentiometric hydrogen sensor which has the capability of detecting hydrogen partial pressure as low as 10 -6 bar or a corrosion rate of 1.5 * 10 -4 μm.a -1 . Preliminary results indicate that a corrosion rate as high as 0.2 μm.a -1 can be sustained for steel coated with salt at 100% RH. Higher corrosion rates (as high as 0.8 μm.a -1 ) were obtained in less humid environment (71% RH). Without a salt deposit, pickled steel in humid environment (as high as 100% RH) also showed detectable corrosion for a period up to 800 hours, during which 0.8 kPa of hydrogen was accumulated prior to the apparent arrest of corrosion, representing a metal loss of 3 nm. Corrosion scales are also identified with x-ray photoelectron spectroscopy (XPS) as well as by mass change monitoring using a quartz crystal microbalance. Corrosion mechanisms and prediction for longer-term exposure will be discussed. Results will be useful in predicting long-term carbon steel corrosion behaviour and improving the current knowledge of hydrogen gas evolution in a deep geological repository for nuclear waste. (authors)

  13. Technology Evaluation for Conditioning of Hanford Tank Waste Using Solids Segregation and Size Reduction

    Restivo, Michael L.; Stone, M. E.; Herman, D. T.; Lambert, Daniel P.; Duignan, Mark R.; Smith, Gary L.; Wells, Beric E.; Lumetta, Gregg J.; Enderlin, Carl W.; Adkins, Harold E.

    2014-04-24

    The Savannah River National Laboratory and the Pacific Northwest National Laboratory team performed a literature search on current and proposed technologies for solids segregation and size reduction of particles in the slurry feed from the Hanford Tank Farm. The team also investigated technology research performed on waste tank slurries, both real and simulated, and reviewed academic theory applicable to solids segregation and size reduction. This review included text book applications and theory, commercial applications suitable for a nuclear environment, research of commercial technologies suitable for a nuclear environment, and those technologies installed in a nuclear environment, including technologies implemented at Department of Energy facilities. Information on each technology is provided in this report along with the advantages and disadvantages of the technologies for this application. Any technology selected would require testing to verify the ability to meet the High-Level Waste Feed Waste Acceptance Criteria to the Hanford Tank Waste Treatment and Immobilization Plant Pretreatment Facility.

  14. Energies and media nr 33. Niger. Conditions for the nuclear sector. Waste disposal

    2010-11-01

    After having evoked the situation of ARLIT's employees who are held as hostages in Niger, and some comments on recent events in the nuclear sector in different countries (energy policy and projects in India, in China, in the USA with opportunities for the French nuclear industry, and in Germany, Belgium, France), this publication discusses the issue of nuclear waste disposal. After having briefly recalled the content of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, it discusses the option of waste storage in deep geological formation, an option which has been chosen by several countries. It questions whether sea beds will ever be a storage option. It comments the case of Germany, of the United States where the storage of high level and long-lived wastes is still facing major problems

  15. Conditions inside Water Pooled in a Failed Nuclear Waste Container and its Effect on Radionuclide Release

    Hamdan, L. K.; Walton, J. C.; Woocay, A.

    2009-12-01

    Nuclear power use is expected to expand in the future, as part of the global clean energy initiative, to meet the world’s surging energy demand, and attenuate greenhouse gas emissions, which are mainly caused by fossil fuels. As a result, it is estimated that hundreds of thousands of metric tons of spent nuclear fuel (SNF) will accumulate. SNF disposal has major environmental (radiation exposure) and security (nuclear proliferation) concerns. Storage in unsaturated zone geological repositories is a reasonable solution for dealing with SNF. One of the key factors that determine the performance of the geological repository is the release of radionuclides from the engineered barrier system. Over time, the nuclear waste containers are expected to fail gradually due to general and localized corrosions and eventually infiltrating water will have access to the nuclear waste. Once radionuclides are released, they will be transported by water, and make their way to the accessible environment. Physical and chemical disturbances in the environment over the container will lead to different corrosion rates, causing different times and locations of penetration. One possible scenario for waste packages failure is the bathtub model, where penetrations occur on the top of the waste package and water pools inside it. In this paper the bathtub-type failed waste container is considered. We shed some light on chemical and physical processes that take place in the pooled water inside a partially failed waste container (bathtub category), and the effects of these processes on radionuclide release. Our study considers two possibilities: temperature stratification of the pooled water versus mixing process. Our calculations show that temperature stratification of the pooled water is expected when the waste package is half (or less) filled with water. On the other hand, when the waste package is fully filled (or above half) there will be mixing in the upper part of water. The effect of

  16. Comments on: ''The use of conditional simulation in nuclear waste site performance assessment''

    Wendelberger, J.; Beckman, R.

    1993-01-01

    In the assessment of underground storage of nuclear waste, at locations like the Waste Isolation Pilot Plan (WIPP) one of the greatest concerns is encroachment of the repository and transportation of radionuclides from the repository to the surrounding environment by the groundwater. This paper demonstrates the contribution that can be made in the studies of this important problem and similar problems of national importance by the application of modern statistical techniques

  17. The role equilibrium leach testing in understanding the behaviour of nuclear wastes under disposal conditions

    Biddle, P.; Rees, J.H.

    1988-01-01

    Results from the equilibrium leach testing of a range of intermediate level nuclear wastes have been modelled successfully using sorption and solubility data obtained in experiments with individual radionuclides. The wastes involved included fuel cladding (after removal of irradiated fuel for reprocessing), combustible plutonium-contaminated materials and ferric/aluminium hydroxide flocs. The test has an important role in validating nearfield models, and helps to build confidence in disposal assessments. (orig.)

  18. Method for the conditioning of high level radioactive wastes for their safe storage and disposal

    Geel, J. van; Eschrich, H.; Detilleux, E.

    1976-01-01

    A method is described for the treatment of solidified high level radioactive wastes to enable them to be safely stored or disposed of in an approved manner. The solidified waste is embedded in a matrix of pure metals or metal alloys. The metals may be Pb, Pb/Sb alloys, Pb/Sn alloys, Pb/Bi alloys, Pb/Zn alloys, or mixtures of these, or Al, Al/Si alloys, Al/Mg alloys, Al/Cu alloys, or mixtures. The matrix is clad with non-corrosive material, selected from stainless steel, Ti, Pb, Pb alloys, Al, Al alloys, or mixtures of same. A non-corrosive container is filled with the solidified waste and is heated to above the melting temperature of the metallic matrix material used to embed the waste. The matrix material is then added and the container is cooled. The container may then be degassed. The solidified waste feed may be in the form of a vitreous material containing the high level waste; this vitreous material may consist of a lead borosilicate or a mixture of non-lead borosilicates and phosphate glasses, and the method of preparing it is described. (U.K.)

  19. Conditioning and storage of low level radioactive waste in FR Yugoslavia

    Plecas, I.; Pavlovic, R.; Pavlovic, S.

    2000-01-01

    FR Yugoslavia is a country without any nuclear power plant on its territory. In the last forty years in the country, as a result of the two research reactors operation and also from radionuclides applications in medicine, industry and agriculture, radioactive waste materials of different levels of specific activity are generated. As a temporary solution, these radioactive waste materials are stored in the two interim storage facility. Since one of the storage facilities is completely full with radioactive wastes, packed in metal drums and plastic barrels, and the second one has an effective space for the next few years, attempts are made in the 'Vinca' Institute of Nuclear Sciences in developing the the immobilization process, for low and intermediate level radioactive wastes and their safe disposal. As an immobilization process, cementation process is investigated. Developed immobilization process has, as a final goal, production of solidified waste-matrix mixture form, that is easy for handling and satisfies requirements for interim storage and final disposal. Radioactive wastes immobilized in inactive matrices are to be placed into concrete containers for further manipulation and disposal

  20. Response of Microbial Community Function to Fluctuating Geochemical Conditions within a Legacy Radioactive Waste Trench Environment.

    Vázquez-Campos, Xabier; Kinsela, Andrew S; Bligh, Mark W; Harrison, Jennifer J; Payne, Timothy E; Waite, T David

    2017-09-01

    During the 1960s, small quantities of radioactive materials were codisposed with chemical waste at the Little Forest Legacy Site (Sydney, Australia) in 3-meter-deep, unlined trenches. Chemical and microbial analyses, including functional and taxonomic information derived from shotgun metagenomics, were collected across a 6-week period immediately after a prolonged rainfall event to assess the impact of changing water levels upon the microbial ecology and contaminant mobility. Collectively, results demonstrated that oxygen-laden rainwater rapidly altered the redox balance in the trench water, strongly impacting microbial functioning as well as the radiochemistry. Two contaminants of concern, plutonium and americium, were shown to transition from solid-iron-associated species immediately after the initial rainwater pulse to progressively more soluble moieties as reducing conditions were enhanced. Functional metagenomics revealed the potentially important role that the taxonomically diverse microbial community played in this transition. In particular, aerobes dominated in the first day, followed by an increase of facultative anaerobes/denitrifiers at day 4. Toward the mid-end of the sampling period, the functional and taxonomic profiles depicted an anaerobic community distinguished by a higher representation of dissimilatory sulfate reduction and methanogenesis pathways. Our results have important implications to similar near-surface environmental systems in which redox cycling occurs. IMPORTANCE The role of chemical and microbiological factors in mediating the biogeochemistry of groundwaters from trenches used to dispose of radioactive materials during the 1960s is examined in this study. Specifically, chemical and microbial analyses, including functional and taxonomic information derived from shotgun metagenomics, were collected across a 6-week period immediately after a prolonged rainfall event to assess how changing water levels influence microbial ecology and

  1. Potential microbial impact on transuranic wastes under conditions expected in the Waste Isolation Pilot Plant (WIPP). Annual report, October 1, 1978-September 30, 1979

    Barnhart, B.J.; Campbell, E.W.; Martinez, E.; Caldwell, D.E.; Hallett, R.

    1980-07-01

    Previous results were confirmed showing elevated frequencies of radiation-resistant bacteria in microorganisms isolated from shallow transuranic (TRU) burial soil that exhibits nanocurie levels of beta and gamma radioactivity. Research to determine whether plutonium could be methylated by the microbially produced methyl donor, methylcobalamine, was terminated when literature and consulting radiochemists confirmed that other alkylated transuranic elements are extremely short-lived in the presence of oxygen. Emphasis was placed on investigation of the dissolution of plutonium dioxide by complex formation between plutonium and a polyhydroxamate chelate similar to that produced by microorganisms. New chromatographic and spectrophotometric evidence supports previous results showing enhanced dissolution of alpha radioactivity when 239 Pu dioxide was mixed with the chelate Desferol. Microbial degradation studies of citrate, ethylenediamine tetraacetate (EDTA), and nitrilo triacetate (NTA) chelates of europium are in progress. Current results are summarized. All of the chelates were found to degrade. The average half-life for citrate, NTA, and EDTA was 3.2, 8.0, and 28 years, respectively. Microbial CO 2 generation is also in progress in 72 tests on several waste matrices under potential WIPP isolation conditions. The mean rate of gas generation was 5.97 μg CO 2 /g waste/day. Increasing temperature increased rates of microbial gas generation across treatments of brine, varying water content, nutrient additions, and anaerobic conditions. No microbial growth was detected in experiments to enumerate and identify the microorganisms in rocksalt cores from the proposed WIPP site. This report contains the year's research results and recommendations derived for the design of safe storage of TRU wastes under geologic repository conditions

  2. Analysis on regional hydrogeological condition of Beishan preselected area for high level radioactive waste disposal repository in Gansu province

    Guo Yonghai; Su Rui; Liu Shufen; Lu Chuanhe

    2004-01-01

    Based on the field investigation which has been carried out in the Beishan preselected area for high level radioactive waste repository in Gansu province during the last few years and the previous hydrogeological investigation results, the different groundwater types are divided initially and the hydrogeological features of different water-bearing media are described in this paper. Meanwhile, the preliminary evaluation of the regional hydrogeological condition of the study area is carried out. (author)

  3. [Investigation of actual condition of management and disposal of medical radioactive waste in Korea].

    Watanabe, Hiroshi; Nagaoka, Hiroaki; Yamaguchi, Ichiro; Horiuchi, Shoji; Imoto, Atsushi

    2009-07-20

    In order to realize the rational management and disposal of radioactive waste like DIS or its clearance as performed in Europe, North America, and Japan, we investigated the situation of medical radioactive waste in Korea and its enforcement. We visited three major Korean facilities in May 2008 and confirmed details of the procedure being used by administering a questionnaire after our visit. From the results, we were able to verify that the governmental agency had established regulations for the clearance of radioactive waste as self-disposal based on the clearance level of IAEA in Korea and that the medical facilities performed suitable management and disposal of radioactive waste based on the regulations and superintendence of a radiation safety officer. The type of nuclear medicine was almost the same as that in Japan, and the half-life of all radiopharmaceuticals was 60 days or less. While performing regulatory adjustment concerning the rational management and disposal of radioactive waste in Korea for reference also in this country, it is important to provide an enforcement procedure with quality assurance in the regulations.

  4. Bio-corrosion for underground disposal of radioactive waste; Biocorrosion en conditions de stockage geologique de dechets radioactifs

    Libert, M.; Esnault, L. [CEA, DEN/DTN/SMTM/LMTE, 13108 St Paul lez Durance, (France); Esnault, L. [ECOGEOSAFE, Technopole environnement Arbois-Mediterranee, avenue Louis Philibert, 13545 Aix-en-Provence Cedex, (France); Feron, D. [CEA, DEN/DANS/DPC, 91191 Gif-sur-Yvette, (France)

    2011-07-01

    The safety disposal of high level nuclear waste (HLNW) is the major breakthrough allowing socially acceptable development of nuclear energy over the coming decades. The French concept for geological disposal of HLNW is based on a multi-barrier system made by metallic containers confined in natural clay. The main alteration parameter is water arriving on waste after the corrosion of metallic components. The anoxic aqueous corrosion phenomena are studied in order to evaluate the confinement capacity of metallic barriers. The discover of active micro-organisms in deep clayey environments raises the question of the impact of micro-organisms on corrosion parameters due to processes such as 'biologically induced corrosion'. Despite of extreme conditions in deep nuclear geological disposal (redox conditions, high pressure and temperature, irradiation), bacterial activity will adapt and survive in these environments. Anoxic corrosion of nuclear waste containers and radiolysis will produce H{sub 2}, which represents a new energetic source for bacterial development, especially in this environment that contains a low amount of biodegradable organic matter. Besides, the formation of Fe(III)-bearing minerals such as magnetite (Fe{sub 3}O{sub 4}) as corrosion products will provide electron acceptors favouring the development of bacteria. Bio-corrosion studies of nuclear waste disposal need to investigate the activity of hydrogenotrophic bacteria able to reduce iron oxides (passivation layer) or sulfates (iron reducing bacteria and sulfate reducing bacteria) in order to evaluate their impact on the long-term stability of metallic compounds involved in multi-barrier system for high-level nuclear waste containment. (authors)

  5. Gasification and co-gasification of biomass wastes: Effect of the biomass origin and the gasifier operating conditions

    Lapuerta, Magin; Hernandez, Juan J.; Pazo, Amparo; Lopez, Julio [Universidad de Castilla-La Mancha, Escuela Tecnica Superior de Ingenieros Industriales (Edificio Politecnico), Avenida Camilo Jose Cela s/n. 13071 Ciudad Real (Spain)

    2008-09-15

    Air gasification of different biomass fuels, including forestry (pinus pinaster pruning) and agricultural (grapevine and olive tree pruning) wastes as well as industry wastes (sawdust and marc of grape), has been carried out in a circulating flow gasifier in order to evaluate the potential of using these types of biomass in the same equipment, thus providing higher operation flexibility and minimizing the effect of seasonal fuel supply variations. The potential of using biomass as an additional supporting fuel in coal fuelled power plants has also been evaluated through tests involving mixtures of biomass and coal-coke, the coke being a typical waste of oil companies. The effect of the main gasifier operating conditions, such as the relative biomass/air ratio and the reaction temperature, has been analysed to establish the conditions allowing higher gasification efficiency, carbon conversion and/or fuel constituents (CO, H{sub 2} and CH{sub 4}) concentration and production. Results of the work encourage the combined use of the different biomass fuels without significant modifications in the installation, although agricultural wastes (grapevine and olive pruning) could to lead to more efficient gasification processes. These latter wastes appear as interesting fuels to generate a producer gas to be used in internal combustion engines or gas turbines (high gasification efficiency and gas yield), while sawdust could be a very adequate fuel to produce a H{sub 2}-rich gas (with interest for fuel cells) due to its highest reactivity. The influence of the reaction temperature on the gasification characteristics was not as significant as that of the biomass/air ratio, although the H{sub 2} concentration increased with increasing temperature. (author)

  6. Study on melting conditions of radioactive miscellaneous solid waste. Contract research

    Fukui, Toshiki; Nakashio, Nobuyuki; Isobe, Motoyasu; Otake, Atsushi; Wakui, Takuji; Nakashima, Mikio; Hirabayashi, Takakuni

    2001-02-01

    Improvement of fluidity of molten slag is one of the most important factors for plasma melting treatment of low level radioactive miscellaneous wastes generated from nuclear facilities. In general, it is considered that elevating molten slag temperature of addition of flux is of certain use in improvement of fluidity of molten slag. However, these ways are not necessarily suitable from the viewpoints of refractory erosion or reduction of waste volume. In this report, we suggested that fluidity of molten slag could be improved by controlling chemical compositions of molten slag. On the Basic of the investigation using phase diagram and viscosity data, FeO was selected as a key component for improving fluidity: Viscosity and melting point of molten slag decreased with increasing relative concentration of FeO in molten slag. Accordingly, we concluded that it is important to adjust basicity of molten slag for melting treatment of low-level radioactive miscellaneous solid wastes. (author)

  7. The role of Tetronics plasma vitrification technology in the management and conditioning of nuclear waste

    Deegan, David; Scales, Charlie

    2007-01-01

    Plasma Arc Technology is finding wider application in the treatment of hazardous waste materials an area which has a lot of synergy with radioactive waste management. It is being stimulated by the increasing demands of regulatory and economic drivers; currently, within the Integrated Waste Management (IWM) sector, there is a climate of rising costs, limited numbers of technological solutions, restricted access to traditional disposal based solutions and a significant levels of market consolidation. Traditionally, the IWM sector has operated with basic mixing technology solutions: e.g. physiochemical consolidation, physiochemical separation, neutralisation and basic material bulking, with ultimate reliance on landfill, cement based encapsulation and high temperature incineration (HTI). The impact of national statutes, the value of national liabilities and infra-structural deficiencies is demanding constant technological advancement for continued regulatory compliance. This paper presents information on Tetronics' plasma based solution, for the treatment of Asbestos Containing Materials (ACM) and Plutonium Containing Material (PCM). (authors)

  8. Modeling of hydrologic conditions and solute movement in processed oil shale waste embankments under simulated climatic conditions. Final report, November 1995

    NONE

    1995-12-31

    A study is described on the hydrological and geotechnical behavior of an oil shale solid waste. The objective was to obtain information which can be used to assess the environmental impacts of oil shale solid waste disposal in the Green River Basin. The spent shale used in this study was combusted by the Lurgi-Ruhrgas process by Rio Blanco Oil Shale Company, Inc. Laboratory bench-scale testing included index properties, such as grain size distribution and Atterberg limits, and tests for engineering properties including hydraulic conductivity and shear strength. Large-scale tests were conducted on model spent shale waste embankments to evaluate hydrological response, including infiltration, runoff, and seepage. Large-scale tests were conducted at a field site in western Colorado and in the Environmental Simulation Laboratory (ESL)at the University of Wyoming. The ESL tests allowed the investigators to control rainfall and temperature, providing information on the hydrological response of spent shale under simulated severe climatic conditions. All experimental methods, materials, facilities, and instrumentation are described in detail, and results are given and discussed. 34 refs.

  9. High energy x-radiographic assessment of conditioned intermediate level waste blocks

    Lewcock, A.I.; Burch, S.F.; Reynolds, W.N.; Pullen, D.A.W.; Smith, D.

    1985-07-01

    This report describes an effective technique for examining the quality of the solidification matrix material in a 500 litre waste drum, testing for homogeneity and major cracks and the confirmation of set. A high energy x-ray source, (an 8 MeV Linac) and a special x-ray TV system, were used to examine several different types of solidified waste form, with and without background radiation, simulated by the use of an uncollimated radiographic isotope. The system as tested showed no discernable image degradation when the isotope was positioned to give a representative background dose as experienced with active ILW monoliths. (author)

  10. Barriers of repository under the conditions of underground isolation of heat releasing radioactive waste in permafrost

    Kazakov, A.N.; Fedorovich, L.N.

    1995-01-01

    The main positions and the leading principle of the ensuring of the environmental safety of the method of the underground isolation of radioactive waste in permafrost rock are presented in this work and it is shown here the peculiarities in realization of the principle of the multibarrier protection. It is substantiated here the principle of the optimal time of the capacity for work of the repository's engineered barriers. The possibility of the exclusion of the radionuclides migration beyond the working volume of the repository during the time of the potential danger of radioactive waste is also substantiated in these papers

  11. Appropriate conditions for applying NaOH-pretreated two-phase olive milling waste for codigestion with food waste to enhance biogas production.

    Al-Mallahi, Jumana; Furuichi, Toru; Ishii, Kazuei

    2016-02-01

    The high methane gas production potential of two phase olive milling waste (2POMW) makes its application to biogas plants in business an economical process to increase the productivity of the plants. The objective of this study was to investigate the appropriate conditions for the codigestion of NaOH-pretreated 2POMW with food waste. NaOH pretreatment can increase the methane production by increasing the soluble chemical oxygen demand (sCOD), but it may cause inhibition because of higher levels of alkalinity, sodium ion, volatile fatty acids and long chain fatty acids (LCFAs). Therefore, the first experimental phase of this study aimed to investigate the effect of different mixing ratios of 2POMW to food waste. A continuous stirred tank reactor experiment with different mixing ratios of 3%, 4.3%, 5.7% and 8.3% (2POMW: food waste) was conducted. NaOH pretreatment in the range of 6-20% was used. A mixing ratio up to 4.3%, when 10% NaOH pretreatment was used, caused no inhibition and increased methane production by 445.9mL/g-VS(2POMW). For this mixing ratio an additional experimental phase was conducted with the 20% NaOH pretreatment as the 20% NaOH pretreatment had the highest sCOD. The methane gas production was increased by 503.6mL/g-VS(2POMW). However, pH adjustment was required for applying this concentration of the high alkalinity 20% NaOH-pretreated 2POMW. Therefore, we consider using 10% NaOH pretreatment in a mixing ratio of 4.3% to be more applicable. The increase in methane gas production was correlated to the oleic acid concentration inside the reactors. The high oleic acid concentration of 61.8mg/L for the 8.3% mixing ratio was responsible for the strong inhibition. This study showed that adjusting the appropriate mixing ratio of the NaOH-pretreated 2POMW could increase the electricity production of a reactor that regularly receives food waste. Copyright © 2015 Elsevier Ltd. All rights reserved.

  12. Simplification and optimisation of treatment/conditioning processes for radioactive waste at Indian Peshawar

    Sharma, P.D.; Chopra, S.K.

    2001-01-01

    Past experience of more than 160 years reactor operation and management of waste generation has established that the methods followed and the controls adopted are adequate though improvement in design with respect to tech no-economic considerations are under development

  13. Training-methodical guide on radioecology and radiation waste management in the Kazakhstan conditions

    2002-01-01

    The guide is compiled with purpose to render assistance to specialists, secondary schools' teachers for elder classes' pupils and population on radioecology and radiation waste management for understanding of a more deep problems in this field. The guide consists of a lot of illustrative and tabular materials including of results of the authors own investigations

  14. Legal boundary conditions of the waste management and energy industry; Rechtliche Rahmenbedingungen der Abfall- und Energiewirtschaft

    Brahms, Florian [Maslaton Rechtsanwaltsgesellschaft mbH, Leipzig (Germany)

    2013-10-01

    The legal framework of waste and energy management was subject to significant transformations which find their legal link of the national state objective to protect the natural resources for future generations in Article 20a of the German constitution. The waste law as well as the energy law aim at the efficient use of resources to protect the environment and smooth the way for a CO{sub 2}-neutral society. After the accident at Fukushima on 11 March 2011 the legislator enacted a number of laws that have a lasting impact on the energy industry and that the operators of biomass plants have to adapt to. At the same time, renewable energies have achieved a remarkable market share under the German Renewable Energy Act, so that market and system integration has also moved into the foreground of the legislation. For electricity produced from the fermentation of biowaste, the German Renewable Energy Act 2012 already provides that the fixed feed-in compensation for installations with an electrical power over 750 kW commissioned after 31 December 2013 no longer exists. The waste legislation is characterized in particular by its relation to European laws, although the definition of the term ''waste'' still causes demarcation difficulties. The Biowaste Ordinance was comprehensively amended in April 2012 in consideration of a number of European regulations. (orig.)

  15. Changes in physical conditions of a coarse textured soil by addition of organic wastes

    Melis Cercioglu

    2014-01-01

    Full Text Available Effects of composted tobacco waste, chicken manure and bio-humus applied during a period of three years on a coarse textured soil (Typic Xerofluvent at Agriculture Faculty’s Research and Practise Farmyard of Ege University located on Menemen plain (Izmir, Turkey on soil physical properties were studied. The experiment was arranged in a randomized block design on 16 plots with four replications. Each plot size was 5x3 m2. Composted tobacco waste (CTW from cigarette industry and chicken manure (CM and bio-humus (BH from plant residuals were applied at rates of 50 t ha-1, 4 t ha-1, 10 t ha-1,respectively. Inorganic fertilizers (N-P-K are also added with chicken manure and bio-humus plots. Tobacco wastes obtained from cigarette industry were used after composting. The addition of organic wastes resulted in a significant (p≤0.05 decrease in bulk density (BD; increase in porosity (PO, field capacity (FC, wilting point (WP, available water content (AWC and structure stability index (SSI of soil samples when compared to the control.

  16. Theoretical analysis of municipal solid waste treatment by leachate recirculation under anaerobic and aerobic conditions

    van Turnhout, A.G.; Brandstätter, Christian; Kleerebezem, R.; Fellner, Johann; Heimovaara, T.J.

    2018-01-01

    Long-term emissions of Municipal Solid Waste (MSW) landfills are a burden for future generations because of the required long-term aftercare. To shorten aftercare, treatment methods have to be developed that reduce long-term emissions. A treatment method that reduces emissions at a lysimeter

  17. Evolution of chemical conditions and estimated solubility controls on radionuclides in the residual waste layer during post-closure aging of high-level waste tanks

    Denham, M. E. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Millings, M. R. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2012-08-28

    This document provides information specific to H-Area waste tanks that enables a flow and transport model with limited chemical capabilities to account for varying waste release from the tanks through time. The basis for varying waste release is solubilities of radionuclides that change as pore fluids passing through the waste change in composition. Pore fluid compositions in various stages were generated by simulations of tank grout degradation. The first part of the document describes simulations of the degradation of the reducing grout in post-closure tanks. These simulations assume flow is predominantly through a water saturated porous medium. The infiltrating fluid that reacts with the grout is assumed to be fluid that has passed through the closure cap and into the tank. The results are three stages of degradation referred to as Reduced Region II, Oxidized Region II, and Oxidized Region III. A reaction path model was used so that the transitions between each stage are noted by numbers of pore volumes of infiltrating fluid reacted. The number of pore volumes to each transition can then be converted to time within a flow and transport model. The bottoms of some tanks in H-Area are below the water table requiring a different conceptual model for grout degradation. For these simulations the reacting fluid was assumed to be 10% infiltrate through the closure cap and 90% groundwater. These simulations produce an additional four pore fluid compositions referred to as Conditions A through D and were intended to simulate varying degrees of groundwater influence. The most probable degradation path for the submerged tanks is Condition C to Condition D to Oxidized Region III and eventually to Condition A. Solubilities for Condition A are estimated in the text for use in sensitivity analyses if needed. However, the grout degradation simulations did not include sufficient pore volumes of infiltrating fluid for the grout to evolve to Condition A. Solubility controls for use

  18. Disposal Of Waste Matter

    Kim, Jeong Hyeon; Lee, Seung Mu

    1989-02-01

    This book deals with disposal of waste matter management of soiled waste matter in city with introduction, definition of waste matter, meaning of management of waste matter, management system of waste matter, current condition in the country, collect and transportation of waste matter disposal liquid waste matter, industrial waste matter like plastic, waste gas sludge, pulp and sulfuric acid, recycling technology of waste matter such as recycling system of Black clawson, Monroe and Rome.

  19. Spent fuel as a waste form: Data needs to allow long term performance assessment under repository disposal conditions

    Oversby, V.M.

    1986-12-01

    Performance assessment calculations are required for high level waste repositories for a period of 10,000 years. The Siting Guidelines require a comparison of sites following site characterization and prior to final site selection to be made over a 100,000 year period. To perform the required calculations, a detailed knowledge of the physical and chemical processes that affect waste form performance will be needed for each site. This paper will review the factors that affect the release of radionuclides from spent fuel under repository conditions, summarize our present state of knowledge, and suggest areas where more work is needed to support the performance assessment calculations. 17 refs., 5 figs., 3 tabs

  20. An assessment of the disposal of radioactive petroleum industry waste in nonhazardous landfills using risk-based modeling

    Smith, K.P.; Arnish, J.J.; Williams, G.P.; Blunt, D.L.

    2003-01-01

    Certain petroleum production activities cause naturally occurring radioactive materials (NORM) to accumulate in concentrations above natural background levels, making safe and cost-effective management of such technologically enhanced NORM (TENORM) a key issue for the petroleum industry. As a result, both industry and regulators are interested in identifying cost-effective disposal alternatives that provide adequate protection of human health and the environment. One such alternative, currently allowed in Michigan with restrictions, is the disposal of TENORM wastes in nonhazardous waste landfills. The disposal of petroleum industry wastes containing radium-226 (Ra-226) in nonhazardous landfills was modeled to evaluate the potential radiological doses and health risks to workers and the public. Multiple scenarios were considered in evaluating the potential risks associated with landfill operations and the future use of the property. The scenarios were defined, in part, to evaluate the Michigan policy; sensitivity analyses were conducted to evaluate the impact of key parameters on potential risks. The results indicate that the disposal of petroleum industry TENORM wastes in nonhazardous landfills in accordance with the Michigan policy and existing landfill regulations presents a negligible risk to most of the potential receptors considered in this study.

  1. Polyhydroxyalkanoate Production on Waste Water Treatment Plants: Process Scheme, Operating Conditions and Potential Analysis for German and European Municipal Waste Water Treatment Plants

    Timo Pittmann

    2017-06-01

    Full Text Available This work describes the production of polyhydroxyalkanoates (PHA as a side stream process on a municipal waste water treatment plant (WWTP and a subsequent analysis of the production potential in Germany and the European Union (EU. Therefore, tests with different types of sludge from a WWTP were investigated regarding their volatile fatty acids (VFA production-potential. Afterwards, primary sludge was used as substrate to test a series of operating conditions (temperature, pH, retention time (RT and withdrawal (WD in order to find suitable settings for a high and stable VFA production. In a second step, various tests regarding a high PHA production and stable PHA composition to determine the influence of substrate concentration, temperature, pH and cycle time of an installed feast/famine-regime were conducted. Experiments with a semi-continuous reactor operation showed that a short RT of 4 days and a small WD of 25% at pH = 6 and around 30 °C is preferable for a high VFA production rate (PR of 1913 mgVFA/(L×d and a stable VFA composition. A high PHA production up to 28.4% of cell dry weight (CDW was reached at lower substrate concentration, 20 °C, neutral pH-value and a 24 h cycle time. A final step a potential analysis, based on the results and detailed data from German waste water treatment plants, showed that the theoretically possible production of biopolymers in Germany amounts to more than 19% of the 2016 worldwide biopolymer production. In addition, a profound estimation regarding the EU showed that in theory about 120% of the worldwide biopolymer production (in 2016 could be produced on European waste water treatment plants.

  2. Assessment of waste management options in the oil and gas industry in Ghana using nuclear analytical techniques

    Ahialey, W. K.

    2013-07-01

    Ghana's oil find is growing steadily as more discoveries are being made. Oil and gas exploration and production coupled with their related activities produce wastes. These wastes could be put into three primary categories such as produced water, drilling cuttings and associated wastes (any other waste related with the exploration, development and production of crude oil or natural gas). These wastes may contain varying amount of contaminants such as heavy metals, suspended solid particles and radioactive materials such as Ra-226 or Rn-228, product of U-238 decay that occur in some geologic formations and sediments. The main objective of this study is to assess the waste management practices in the oil and gas industry in Ghana by qualification and quantification of waste generated during exploration and production, examining the system put in place by oil and gas companies to manage these wastes and also determine some basic contaminants in some of these wastes brought to shore for management. Waste samples were taken from Tema Oil Refinery (TOR) and Zeal Environmental Technology Limited at Takoradi. The samples were analyzed by Neutron Activation Analysis (NAA) and Flame Atomic Absorption Spectrometry (FAAS) analytical methods to determine heavy metals (Pb, Cd, Cr, Hg, As, Ag, Ba, Se) in the oily waste water, oil based mud, block and ash samples. The results showed that the levels of heavy metals were below the EPA permissible limit for discharge into the natural drainage except the level of Pb in the mud samples taken from Zeal before treatment. The levels ranged from 3.99mg/l to 7.44mgl. Even though these levels were above 0.1mg/l discharge standard limit, there was no cause for alarm because the levels dropped below the EPA limit after treatment. Furthermore, the quantity of general garbage deposited in the landfill at Takoradi be Zeal Environmental Technology Limited from 2011 to 2012 increased from 497m 3 to 1,314.29m 3 respectively. (author)

  3. A Simple Mathematical Model of the Anaerobic Digestion of Wasted Fruits and Vegetables in Mesophilic Conditions

    Elena Chorukova

    2015-04-01

    Full Text Available Anaerobic digestion is an effective biotechnological process for treatment of different agricultural, municipal and industrial wastes. Use of mathematical models is a powerful tool for investigations and optimisation of the anaerobic digestion. In this paper a simple mathematical model of the anaerobic digestion of wasted fruits and vegetables was developed and verified experimentally and by computer simulations using Simulink. A three-step mass-balance model was considered including the gas phase. The parameter identification was based on a set of 150 days of dynamical experiments in a laboratory bioreactor. Two step identification procedure to estimate 4 model parameters is presented. The results of 15 days of experiment in a pilot-scale bioreactor were then used to validate the model.

  4. Cement conditioning of waste materials and polluted soil using the GEODUR process

    Brocdersen, K.; Hjelmar, O.; Mortonsen, S.

    1991-01-01

    In this paper two areas of application of the GEODUR additive in cement stabilization of waste materials have been investigated: stabilization of radioactive contaminated soil and stabilization of municipal solid waste incinerator ash. Preliminary experimental work on a clayey soil contaminated with radioactive cesium and strontium has indicated that the GEODUR process is a technically feasible method for soil solidification. The retarding effects of humic materials in the soil are eliminated by the additive even at low cement contents. The solidified soil is not particularly strong, but that satisfactory water permeability. Retention of cesium is reasonably good, but not as good as for the untreated soil. Retention of strontium is not good but is considerably improved by carbonation. The volume stability during permanent immersion of the solidified products in water is satisfactory, but crack formation during dryout cannot be excluded

  5. Physical and enzymatic conditioning of oenological wastes to improve biogas production

    Bracchitta, Mirko

    2012-01-01

    A fundamental assumption for by-product from winery industy waste-management is their economic and commercial increase in value. High energetic value recovery from winery industry is an attractive economic solution to stimulate new sustainable process. Approach of this work is based about physic and biological treatment with grape stalks and grape marc to increase polysaccharides components of cell wall and energetic availability of this by-products. Grape stalks for example have a high perce...

  6. Possibility of disposing of conditioned nuclear waste in deep-lying clay formations

    Bonne, A.; Heremans, R.; Vandenberghe, N.

    1980-01-01

    Among the host rock types suitable for final disposal of nuclear waste, argillaceous formations display distinct advantages and disadvantages. In the present paper some of them will be examined. In order to render conceivable the possibilities for disposing of radwastes into a plastic clay formation, some main items of the Belgian R and D-programme in that matter will be discussed (site and rock investigation, conceptual design and feasibility, and risk analysis). (Auth.)

  7. Conditioning of solid radioactive wastes (1960); Conditionnement des dechets radioactifs solides (1960)

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

    1960-07-01

    Since solid radioactive wastes are of varied forms, dimensions and volumes, the C.E.A. first reduces the volume by breaking up and compacting. Since these wastes cannot be temporarily stored without contamination risk, an effective packing process has been devised and carried through. This consists in burying the wastes in a specially planned concrete with the following characteristics: - high mechanical resistance; - maximum insolubility; - resistance to corrosion; - maximum imperviousness; - providing protection against radiation. It is then possible to store the blocks safely, with a view to eventual definitive rejection. (author) [French] Les dechets actifs solides etant de formes, de dimensions et de volumes varies, le C.E.A. procede en premier lieu a une reduction de volume par fractionnement et compactage. L'emmagasinage provisoire de tels dechets ne pouvant se concevoir sans risques de contamination, un procede efficace d'emballage a ete etudie et realise. Il consiste a noyer les dechets dans un beton specialement etudie qui presente les caracteristiques suivantes: - forte resistance mecanique; - insolubilite maximum; - resistance a la corrosion; - etancheite maximum; - protection contre le rayonnement. Il est alors possible de conserver sans danger les blocs formes en vue d'un rejet definitif ulterieur. (auteur)

  8. Treatment and Conditioning of Radioactive Waste Solution by Natural Clay Minerals

    El-Dessouky, M.I.; Abdel-Raouf, M.W.; El-Massry, E.H.; Khalifa, S.M.; Aly, H.F.

    1999-01-01

    Chemical precipitation processes have been used for the treatment of radioactive elements from aqueous solution. The volume reduction is not very great and storage facilities are expensive. There are some radionuclides which are so difficult to be precipitated by this common method, so they may be precipitated by adding solid materials such as natural inorganic exchangers. In this woek, improvement the removal of caesium, cobalt and europium with zinc sulfate as coagulant and different clay minerals have been investigated. These include, Feldespare, Aswanly, Bentionite, Hematite, Mud, Calcite, Basalt, Magnetite, Kaoline, Sand stone, Limonite and Sand. The parameters affecting the precipitation process such as pH, particle size, temperature and weight of the clay have been studied. The results indicate that, the highest removal for Cs-137, Co-60 and Eu-152 and154 by Asswanly, Bentonite and Sand stone is more than the other clays. Removal of Cs-137 from low level waste solution with these three natural clays took the sequence, Aswanly (85.5%) > Bentonite (82.2%) > Sandstone (65.4%). Solidified cement products have been evaluated to determine mechanical strength and leaching rates of the waste products. The solidified waste forms were found more acceptable for handling ,storage and ultimate disposal

  9. Batch anaerobic co-digestion of Kimchi factory waste silage and swine manure under mesophilic conditions.

    Kafle, Gopi Krishna; Kim, Sang Hun; Sung, Kyung Ill

    2012-11-01

    The objective of this study was to investigate the feasibility of anaerobic co-digestion of Kimchi factory waste silage (KFWS) with swine manure (SM). Chinese cabbage (CC) is the major waste generated by a Kimchi factory and KFWS was prepared by mixing CC and rice bran (RB) (70:30 on a dry matter basis). In Experiment I, the biogas potential of CC and RB were measured and, in Experiment II, the test was conducted with different ratios of KFWS and SM (KFWS: SM=0:100; 33:67; 67:33; 100:0 by% volatile solids (VS) basis). KFWS produced a 27% higher biogas yield and a 59% higher methane yield compared to CC. The specific biogas yields increased by 19, 40 and 57% with KFWS-33%, KFWS-67% and KFWS-100%, respectively compared to SM-100% (394 mL/g VS). Similarly, VS removal increased by 37, 51 and 74% with KFWS-33%, KFWS-67% and KFWS-100%, respectively compared to SM-100%. These results suggested that Kimchi factory waste could be effectively treated by making silage, and the silage could be used as a potential co-substrate to enhance biogas production from SM digesters. Copyright © 2012 Elsevier Ltd. All rights reserved.

  10. Radium migration of thorium deposit of Morro do Ferro (Pocos de Caldas, MG, Brazil) under conditions of no rainfall (baseflow regime)

    Campos, M.J.M.T. de.

    1984-01-01

    The mechanisms of radium leaching and transport at the Morro do Ferro are investigated to estimate the 228 Ra mobilization rate, under conditions of no rainfall (baseflow regime). Radium was analysed in solution and in suspended solids, in surface and ground waters at the Morro do Ferro general basin Ra-226 was determined by the radon emanation method and 228 Ra through the radiometry of its first daughter 228 Ac. Initially, a radiochemical procedure was employed for 228 Ra, which performs the purification of radium by coprecipitation with BaSO 4 , and the separation of 228 Ac by coprecipitation with LaF 3 , which is then beta counted. At the later phase of this work the samples were analyzed by the radiometric method which is based on the radiometry of β-γ 228 Ac coincidence transitions. (M.A.C.) [pt

  11. Global warming potential of material fractions occurring in source-separated organic household waste treated by anaerobic digestion or incineration under different framework conditions

    Naroznova, Irina; Møller, Jacob; Scheutz, Charlotte

    2016-01-01

    This study compared the environmental profiles of anaerobic digestion (AD) and incineration, in relation to global warming potential (GWP), for treating individual material fractions that may occur in source-separated organic household waste (SSOHW). Different framework conditions representative...

  12. Why building capacity is a necessary but insufficient condition for improved waste management in South Africa: The knowledge–behaviour relationship

    Godfrey, Linda K

    2010-10-01

    Full Text Available beliefs form behavioural intentions which result in behaviour. Findings show that building capacity, which support control beliefs, while certainly a necessary condition, is insufficient to change waste behaviour. Consideration needs to be given...

  13. [Measurement and analysis of micropore aeration system's oxygenating ability under operation condition in waste water treatment plant].

    Wu, Yuan-Yuan; Zhou, Xiao-Hong; Shi, Han-Chang; Qiu, Yong

    2013-01-01

    Using the aeration pool in the fourth-stage at Wuxi Lucun Waste Water Treatment Plant (WWTP) as experimental setup, off-gas method was selected to measure the oxygenating ability parameters of micropore aerators in a real WWTP operating condition and these values were compared with those in fresh water to evaluate the performance of the micropore aerators. Results showed that the micropore aerators which were distributed in different galleries of the aeration pool had significantly different oxygenating abilities under operation condition. The oxygenating ability of the micropore aerators distributed in the same gallery changed slightly during one day. Comparing with the oxygenating ability in fresh water, it decreased a lot in the real aeration pool, in more details, under the real WWTP operating condition, the values of oxygen transfer coefficient K(La) oxygenation capacity OC and oxygen utilization E(a) decreased by 43%, 57% and 76%, respectively.

  14. Conditioning of cladding waste for long-term storage by press compaction and encapsulation in lead containment

    Regge, P. de

    1986-01-01

    The conditioning of compacted cladding waste has been based on the concept of a corrosion-resistant containment. The technique of press compaction in remote operation conditions has been demonstrated. Detailed specifications of the design of the container are discussed in the report. Testing procedures for the different containment parts have been developed and applied. The remote welding techniques of the stainless steel and lead-based parts of the containment have been investigated and reliable procedures are reported. A technique for remote leak-testing of welded containers is described. The report contains a series of pictures documenting the entire conditioning concept, starting from the dissolver basket at the reprocessing stage up to the final disposal container

  15. Radioactive waste management

    2013-01-01

    This eighth chapter presents the radioactive wastes and waste disposal; classification of radioactive wastes; basis requests of the radioactive waste management; conditions for a radioactive waste disposal; registers and inventories; transport of radioactive wastes from a facility to another and the radioactive waste management plan

  16. Medium activity long-lived nuclear waste; microbial paradise or hadean environment - Evaluation of biomass and impact on redox conditions

    Albrecht, A.; Libert, M.

    2010-01-01

    Document available in extended abstract form only. The evaluation of the impact of possible microbial activity in nuclear waste cells has been a subject for more than a quarter of a century. Some of the items of interest in relation to microbial impact on near field biogeochemistry indicated in Table 1 had already been known as pertinent. Recently, it became clear that a distinction needed to be made between high-level, vitrified waste and organic matter containing intermediate-level waste, of which the bituminized waste is used as an example here. For high-level waste the canister walls play an important safety role and the most probable limiting aspects, next to space and water, are the low concentrations in organic matter as a carbon source and phosphorous and nitrogen as essential elements. In this particular case, microbially induced corrosion is of primary concern. In the case of the French intermediate bituminized waste, primary interest is on the impact of microbial activity on redox reactions, with the high pH environment, as a consequence of the concrete engineered barrier, as the most probable limiting condition. The canister wall has no explicit long-term safety role and all components for microbial activity will become readily available. The presence of nitrates, sulphates and Fe(III) as electron acceptors and organic matter, hydrogen gas and zero-valent metals (i.e. Fe) as electron donors allows the system to supply energy for bacterial activity and to move through the entire redox sequence from O 2 (present only shortly after waste-cell closure) to nitrate, Fe(III), sulphate and organic matter reduction. Prevailing uncertainties do not allow specification of timing for the redox-changes. These uncertainties are essentially related to the lack of knowledge regarding microbial catalysis. As no natural or anthropogenic analogues are available, parameters need to be obtained from experiments. Two approaches will be presented that allow estimation of the

  17. Conditioning of alpha and beta-gamma ashes of incinerator, obtained by radioactive wastes incinerating and encapsulation in several matrices

    Kertesz, C.J.; Chenavas, P.R.; Auffret, L.

    1993-01-01

    In this final report, the work carried out, and the results, obtained on the ash incinerator conditioning study, by means of encapsulation in several matrices, are presented. Three encapsulation matrices were checked: - a ternary cement, containing OPC, blast furnace slag and flying ash, - a two component epoxide system, - an epoxide-cement compound matrix. Three ash categories were employed: - real alpha ash, coming from plutonium bearing wastes, - ash, from inactive combustible waste, obtained by treatment in an incinerator prototype, - ash coming from inactive waste incineration plant. Using three different matrices, the encapsulated form properties were determined: at the laboratory scale, the encapsulating formulation was established, and physico mechanical data were obtained, - on active encapsulated forms, containing a calculated amount of 238 Pu, a radiolysis study was performed in order to measure the composition and volume of the radiolytic gas flow, - at the industrial scale, a pilot plant operating the polyvalent encapsulating process, was designed and put into service. Bench-scale experiments were done, on alpha ash embedded forms using the modified sulphur cement matrix as embedding agent. 4 refs., 30 figs., 27 tabs

  18. Effect of addition of organic waste on reduction of Escherichia coli during cattle feces composting under high-moisture condition.

    Hanajima, Dai; Kuroda, Kazutaka; Fukumoto, Yasuyuki; Haga, Kiyonori

    2006-09-01

    To ensure Escherichia coli reduction during cattle feces composting, co-composting with a variety of organic wastes was examined. A mixture of dairy cattle feces and shredded rice straw (control) was blended with organic wastes (tofu residue, rice bran, rapeseed meal, dried chicken feces, raw chicken feces, or garbage), and composted using a bench-scale composter under the high-moisture condition (78%). The addition of organic waste except chicken feces brought about maximum temperatures of more than 55 degrees C and significantly reduced the number of E. coli from 10(6) to below 10(2)CFU/g-wet after seven days composting, while in the control treatment, E. coli survived at the same level as that of raw feces. Enhancements of the thermophilic phase and E. coli reduction were related to the initial amount of easily digestible carbon in mass determined as BOD. BOD value more than 166.2 mg O2/DMg brought about significant E. coli reduction.

  19. Leaching of the simulated borosilicate waste glasses and spent nuclear fuel under a repository condition

    Kim, Seung Soo; Chun, Kwan Sik; Kang, Chul Hyung; Suh, Hang Suk

    2002-12-01

    Leaching behaviors of simulated waste glass and spent fuel, contacted on bentonite blocks, in synthetic granitic groundwater were investigated in this study. The leach rate of boron from borosilicate waste glass between the compacted bentonite blocks reached about 0.03 gm-2day-1 at 1500 days, like as that of molybdenum. However, the concentration of uranium in leachate pass through bentonite blocks was less than their detection limits of 2 μg/L and whose yellow amorphous compound was found on the surface of glass contacted with the bentonite blocks. The leaching mechanism of waste glasses differed with their composition. The release rate of cesium from PWR spent fuel in the simulated granitic water without bentonite was leas than $1.0x10 -5 fraction/day after 300 days. The retardation factor of cesium by a 10 -mm thickness of bentonite block was more than 100 for 4-years leaching time. The cumulative release fraction of uranium for 954 days was 0.016% (1.7x10 -7 fraction/day) in granitic water without bentonite. The gap inventory of cesium for spent fuel G23-J11 was 0.15∼0.2%. However, the release of cesium from C15-I08 was 0.9% until 60 days and has being continued after that. Gap inventories of strontium and iodine in G23-J11 were 0.033% and below 0.2%, respectively. The sum of fraction of cesium in gap and grain boundary of G23-J11 was suggested below 3% and less

  20. Conditioning of low level radioactive waste at the Research Centre Seibersdorf

    Chalupa, G.; Petschnik, G.

    1986-09-01

    The conditioning (solidification) of LLW at the Austrian Research Centre Seibersdorf are explained. In first part of this paper the comentation of ashes are described and criterias for the application of recipes for conditioning, quality inspection, determination of leaching rates are given. Enclosed to that some figures show you the installed equipment and the handling for conditioning of LLW at the Research Centre. (Author)

  1. Radioactive Waste Treatment and Conditioning Using Plasma Technology Pilot Plant: Testing and Commissioning

    Rafizi Salihuddin; Rohyiza Baan; Norasalwa Zakaria

    2016-01-01

    Plasma pilot plant was commissioned for research and development program on radioactive waste treatment. The plant is equipped with a 50 kW direct current of non-transferred arc plasma torch which mounted vertically on top of the combustion chamber. The plant also consists of a dual function chamber, a water cooling system, a compress air supply system and a control system. This paper devoted the outcome after testing and commissioning of the plant. The problems arise was discussed in order to find the possible suggestion to overcome the issues. (author)

  2. Full scale treatment of phenolic coke coking waste water under unsteady conditions

    Suschka, Jan [Institute for Ecology of Industrial Areas, Katowice (Poland); Morel, Jacek; Mierzwinski, Stanislaw; Januszek, Ryszard [Coke Plant Przyjazn, Dabrowa Gornicza (Poland)

    1993-12-31

    Phenolic waste water from the largest coke coking plant in Poland is treated at a full technical scale. From the very beginning it became evident that very high qualitative variations in short and long periods were to be expected. For this purpose, the biological treatment plant based on activated sludge is protected through preliminary physical-chemical treatment and the results are secured by a final chemical stage of treatment. Nevertheless, improvements in the performance of the treatment plant have been found necessary to introduce. In this work, the experience gained over the last five years is described and developed improvements were presented. 3 refs., 9 figs., 1 tab.

  3. Full scale treatment of phenolic coke coking waste water under unsteady conditions

    Suschka, Jan [Institute for Ecology of Industrial Areas, Katowice (Poland); Morel, Jacek; Mierzwinski, Stanislaw; Januszek, Ryszard [Coke Plant Przyjazn, Dabrowa Gornicza (Poland)

    1994-12-31

    Phenolic waste water from the largest coke coking plant in Poland is treated at a full technical scale. From the very beginning it became evident that very high qualitative variations in short and long periods were to be expected. For this purpose, the biological treatment plant based on activated sludge is protected through preliminary physical-chemical treatment and the results are secured by a final chemical stage of treatment. Nevertheless, improvements in the performance of the treatment plant have been found necessary to introduce. In this work, the experience gained over the last five years is described and developed improvements were presented. 3 refs., 9 figs., 1 tab.

  4. Chemical Studies on the treatment and Conditioning of Radioactive Liquid Waste Using Combined Processes

    El-Masry, E.H.

    2004-01-01

    Natural inorganic exchanges were used to remove radioactive isotopes cesium, Cobalt and europium using coagulant zinc sulfate as coagulant from low level liquid radioactive waste. the highest percent of removal was obtained in the order asswanlly (85.5%), bentonite (82.2%) and sandstone (65.4%) for the removal of cesium . the same order of removal percent was detected for the removal of cobalt (92.5,91.2,90.6%) and europium (90.6,90.8,90.2%) for asswanlly, bentonite and sandstone respectively

  5. Stability assessment of lycopene microemulsion prepared using tomato industrial waste against various processing conditions.

    Amiri-Rigi, Atefeh; Abbasi, Soleiman

    2017-11-01

    Green separation techniques are growing at a greater rate than solvent extraction as a result of the constant consumer drive to 'go natural'. Considering the increasing evidence of the health benefits of lycopene and massive tomato industrial waste, in the present study, lycopene was extracted from tomato industrial waste using microemulsion technique and its mean droplet size and size distribution was determined. Moreover, the effects of pasteurization, sterilization, freeze-thaw cycles and ultraviolet (UV) irradiation on the thermodynamic stability, turbidity and lycopene concentration of the lycopene microemulsion were monitored. Freeze-thaw cycles, pasteurization and short exposure to UV irradiation showed no or negligible influence on lycopene content and turbidity of the microemulsion. However, long exposure to UV (260 min) reduced the lycopene content and turbidity by 34% and 10%, respectively. HHST (higher-heat shorter-time) and sterilization also reduced lycopene content (25%) and increased turbidity (32%). The lycopene microemulsion showed satisfactory stability over a process where its monodispersity and nanosize could be of potential advantage to the food and related industries. Regarding the carcinogenicity of synthetic colourants, potential applications of the lycopene microemulsion include in soft drinks and minced meat, which would result in a better colour and well-documented health-promoting qualities. © 2017 Society of Chemical Industry. © 2017 Society of Chemical Industry.

  6. Properties of slate mining wastes incubated with grape marc compost under laboratory conditions.

    Paradelo, Remigio; Moldes, Ana Belén; Barral, María Teresa

    2009-02-01

    The effect of the addition of spent grape marc compost (GMC) and vermicompost (GMV) as amendments to slate mining wastes was evaluated in a laboratory incubation experiment. Mixtures of slate processing fines (SPF), with three doses of each amendment (4%, 8% and 16% compost, dry weight), plus a control were incubated at 25 degrees C in the laboratory for 90 days. The changes in the chemical and biological properties of the mixtures (pH, total C, total N, inorganic N, available nutrients, microbial biomass carbon and dehydrogenase activity) were investigated during the incubation period, and once it was finished, the phytotoxicity of the mixtures was determined by the germination of Lolium multiflorum Lam. seeds. The addition of the amendments significantly increased the nutrient concentrations of the SPF and enhanced biological activity by increasing microbial biomass and enzymatic activity. Results improved with higher doses; within the composts, GMV showed a better performance than GMC. These results prove the suitability of grape marc-derived amendments for the biochemical amelioration of mining wastes, and highlight the benefits of organic amendment in restoration projects.

  7. Transient boundary conditions in the frame of THM-processes at nuclear waste repositories

    Schanz Tom

    2016-01-01

    Full Text Available In nuclear waste repositories, initially unsaturated buffer is subjected to constant heat emitted by waste canister in conjunction with peripheral hydration through water from host rock. The transient hydration process can be potraied as transformation of initial heterogeneity towards homogeneity as final stage. In this context, this paper addresses the key issue of hydro mechanical behaviour of compacted buffer in context of clay microstructure and its evolution under repository relevant loading paths and material heterogeneity. This paper also introduces a unique column experiment facility available at Ruhr Universität Bochum, Germany. The facility has been designed as a forerunner of field scale testing program to simulate the transient hydration process of compacted buffer as per German reference disposal concept. The device is unique in terms of having proficiency to capture the transient material response under various possible repository relevant loading paths with higher precision level by monitor the key parameters like temperature, total suction, water content and axial & radial swelling pressure at three different sections along the length of compacted soil sample. In general, a larger spectrum of loading paths/scenarios, which may arise in the nuclear repository, can be covered precisely with existing device.

  8. Environmental impact assessment for a radioactive waste facility: A case study

    Devgun, J.S.

    1990-01-01

    A 77-ha site, known as the Niagara Falls Storage Site and located in northwestern New York State, holds about 190, 000 m 3 of soils, wastes, and residues contaminated with radium and uranium. The facility is owned by the US Department of Energy. The storage of residues resulting from the processing of uranium ores started in 1944, and by 1950 residues from a number of plants were received at the site. The residues, with a volume of about 18,000 m 3 , account for the bulk of the radioactivity, which is primarily due to Ra-226; because of the extraction of uranium from the ore, the amount of uranium remaining in the residues is quite small. An analysis of the environmental impact assessment and environmental compliance actions taken to date at this site and their effectiveness are discussed. This case study provides an illustrative example of the complexity of technical and nontechnical issues for a large radiative waste facility. 11 refs., 7 figs., 2 tabs

  9. Development of thermal conditioning technology for alpha-contaminated wastes: a study on leaching characteristics and long-term safety assessment of simulated waste forms

    Seo, Yong Chil [Yonsei University, Seoul (Korea); Lee, Sang Hoon; Yoo, Jong Ik; Choi, Yong Cheol [Yonsei University, Seoul (Korea)

    2001-04-01

    Radioactive wastes should be stabilized for safe management during several hundred years. To assess stability of solidified waste forms, mechanical properties and chemical durability of the waste forms should be analyzed. Chemical durability is one of the most important factors in the assessment of waste forms, which could be examined by leaching tests. Various methods in leaching test are suggested by different organizations, but a formal test method in Korea is not ready yet. Therefore, the leaching test method applicable to various constituents is necessary for the safe management of radioactive wastes In this study, leaching behavior and characteristics of components such as solidification materials, heavy metals and radioactive nuclids were analyzed for cement waste form and glassy waste form. 58 refs., 25 figs., 8 tabs. (Author)

  10. Microbial impacts on 99mTc migration through sandstone under highly alkaline conditions relevant to radioactive waste disposal.

    Smith, Sarah L; Boothman, Christopher; Williams, Heather A; Ellis, Beverly L; Wragg, Joanna; West, Julia M; Lloyd, Jonathan R

    2017-01-01

    Geological disposal of intermediate level radioactive waste in the UK is planned to involve the use of cementitious materials, facilitating the formation of an alkali-disturbed zone within the host rock. The biogeochemical processes that will occur in this environment, and the extent to which they will impact on radionuclide migration, are currently poorly understood. This study investigates the impact of biogeochemical processes on the mobility of the radionuclide technetium, in column experiments designed to be representative of aspects of the alkali-disturbed zone. Results indicate that microbial processes were capable of inhibiting 99m Tc migration through columns, and X-ray radiography demonstrated that extensive physical changes had occurred to the material within columns where microbiological activity had been stimulated. The utilisation of organic acids under highly alkaline conditions, generating H 2 and CO 2 , may represent a mechanism by which microbial processes may alter the hydraulic conductivity of a geological environment. Column sediments were dominated by obligately alkaliphilic H 2 -oxidising bacteria, suggesting that the enrichment of these bacteria may have occurred as a result of H 2 generation during organic acid metabolism. The results from these experiments show that microorganisms are able to carry out a number of processes under highly alkaline conditions that could potentially impact on the properties of the host rock surrounding a geological disposal facility for intermediate level radioactive waste. Copyright © 2016. Published by Elsevier B.V.

  11. A research on thermoelectric generator's electrical performance under temperature mismatch conditions for automotive waste heat recovery system

    Z.B. Tang

    2015-03-01

    Full Text Available The thermoelectric generators recover useful energy by the function of thermoelectric modules which can convert waste heat energy into electricity from automotive exhaust. In the actual operation, the electrical connected thermoelectric modules are operated under temperature mismatch conditions and then the problem of decreased power output causes due to the inhomogeneous temperature gradient distribution on heat exchanger surface. In this case study, an individual module test system and a test bench have been carried out to test and analyze the impact of thermal imbalance on the output electrical power at module and system level. Variability of the temperature difference and clamping pressure are also tested in the individual module measurement. The system level experimental results clearly describe the phenomenon of thermoelectric generator's decreased power output under mismatched temperature condition and limited working temperature. This situation is improved with thermal insulation on the modules and proved to be effective.

  12. TECHNOLOGY EVALUATION FOR CONDITIONING OF HANFORD TANK WASTE USING SOLIDS SEGREGATION AND SIZE REDUCTION

    Restivo, M.; Stone, M.; Herman, D.; Lambert, D.; Duignan, M.; SMITH, G.; WELLS, B.; LUMETTA, G.; ENDRELIN, C.; ADKINS, H.

    2014-04-15

    The Savannah River National Laboratory (SRNL) and the Pacific Northwest National Laboratory (PNNL) team performed a literature search on current and proposed technologies for solids segregation and size reduction of particles in the slurry feed from the Hanford Tank Farm (HTF). The team also investigated technology research performed on waste tank slurries, both real and simulated, and reviewed academic theory applicable to solids segregation and size reduction. This review included text book applications and theory, commercial applications suitable for a nuclear environment, research of commercial technologies suitable for a nuclear environment, and those technologies installed in a nuclear environment, including technologies implemented at Department of Energy (DOE) facilities. Information on each technology is provided in this report along with the advantages and disadvantages of the technologies for this application.

  13. Physical properties of granite relevant to near field conditions in a nuclear waste depository

    McLaren, J.R.; Titchell, I.

    1981-10-01

    This report presents results of the effects of heat and time at temperature on Young's modulus of granite pertinent to fission product heating in a depository for radioactive waste. In general, modulus remains constant at approximately 65 GPa to 60 to 80 0 C and then falls in nearly linear fashion to approximately 6 GPa at 550 0 C. This effect is ascribed to cracking due to differential thermal expansion between the constituent minerals or between differently oriented crystals of the same mineral. An attempt has been made to quantify the extent of cracking and hence calculate an increase in surface area exposed of between 10 2 and 10 3 m 2 .m -3 of rock by heating to 200 0 C. The effects of overburden pressure have not been studied. (author)

  14. Air conditioning using waste heat from fuel cells; Konzeptstudie: Klimatisierung durch Abwaermenutzung aus Brennstoffzellen - Schlussbericht

    Gantenbein, P.; Luzzi, A.; Spirig, M. [Hochschule fuer Technik Rapperswil (HSR), Institut fuer Solartechnik (SPF), Rapperswil (Switzerland); Schuler, A.; Nerlich, V. [Hexis AG, Winterthur (Switzerland)

    2007-07-01

    This concept study for the Swiss Federal Office of Energy (SFOE) reports on work done at the University of Applied Sciences in Rapperswil, Switzerland on possibilities of using the waste heat from fuel cell stacks to provide heating and, in the summertime, cooling using an absorption refrigeration system. The study evaluates the technical, economical and market-relevant aspects of such systems. The methods used in making comparisons with conventional reference systems, including reviews of existing information and expert questioning, are discussed. The results obtained are presented and the results of sensitivity analyses are discussed. These include electricity feed-in tariffs and gas prices, pay-back times, capital interest rates, etc. Further, barriers encountered such as patents and other market hindrances are discussed. The report is completed with a comprehensive appendix.

  15. The mechanical and physical behaviour on the cemented waste forms after one year disposal of real conditions

    Bucataru-Nicu, M.; Mihai, F.; Rotarescu, Gh.; Turcanu, C.N.; Lungu, L.

    1999-01-01

    To prove the durability of cemented waste forms, an experimental program started in 1997 to establish the alteration in time of mechanical and physic-chemical properties of different simulated and real matrices in laboratory and Baita-Bihor disposal conditions. The selected matrices for characterization are normal cement and concrete compositions with and without mineral additives (bentonite and volcanic tuff) as reference samples, the conditioned matrices prepared with radioactive sludge non-active components (iron hydroxides and phosphate, calcium phosphate and cooper ferrocyanide) and non-active matrices prepared with organic acids and salts (oxalic, citric, tartaric, EDTA). All samples will be positioned in five locations of Baita-Bihor repository and kept 1, 3, 5 and 10 years before mechanical and structural characterization. These locations have different humidity conditions decreasing from location 1 to 5. These results will be compared with results obtained for the same type of samples kept in laboratory conditions. The research program requires detailed identification of the complex phenomena involved, long investigation times and extending basic data determined from laboratory tests in simplified conditions. The basic information on the waste matrix are obtained by mechanical strength tests. In this program, up to now, samples were prepared and disposed as follows: 1)cement-water with cement/water ratio 2:1 and 2)cement-sand-water with a cement/sand/water ratio 1:2:0.5. For the mechanical tests the sizes of the samples were: 40 x 40 x 160 mm (tested at bending and compression) and 20 x 20 x 20 mm (tested at compression). After the preparation, the samples were kept 24 hours in pattern, then in tight plastic bag for 7, 14 and 28 days for reinforcement. The bending and compression tests were done in a construction materials laboratory, using an electric press machine. After 28 days the samples of reference were introduced in the National Repository. Some of

  16. Handling, treatment, conditioning and storage of biological radioactive wastes. Technical manual for the management of low and intermediate level wastes generated at small nuclear research centres and by radioisotope users in medicine, research and industry

    1994-12-01

    Biological materials that contain radioactive isotopes have many important applications. During the production and use of these materials, waste will inevitably arise which must be managed with particular care due to their potential biological as well as radiological hazards. This report deals with wastes that arise outside the nuclear fuel cycle and is directed primarily to countries without nuclear power programmes. It is intended to provide guidance to Member States in the handling, treatment and conditioning of biological radioactive materials. The objective of radioactive waste management is to handle, pretreat, treat, condition, store, transport and dispose of radioactive waste in a manner that protects human health and the environment without imposing undue burdens on future generations. 31 refs, 15 figs, 3 tabs

  17. Handling, treatment, conditioning and storage of biological radioactive wastes. Technical manual for the management of low and intermediate level wastes generated at small nuclear research centres and by radioisotope users in medicine, research and industry

    NONE

    1994-12-01

    Biological materials that contain radioactive isotopes have many important applications. During the production and use of these materials, waste will inevitably arise which must be managed with particular care due to their potential biological as well as radiological hazards. This report deals with wastes that arise outside the nuclear fuel cycle and is directed primarily to countries without nuclear power programmes. It is intended to provide guidance to Member States in the handling, treatment and conditioning of biological radioactive materials. The objective of radioactive waste management is to handle, pretreat, treat, condition, store, transport and dispose of radioactive waste in a manner that protects human health and the environment without imposing undue burdens on future generations. 31 refs, 15 figs, 3 tabs.

  18. Performance analysis of waste heat recovery with a dual loop organic Rankine cycle (ORC) system for diesel engine under various operating conditions

    Yang, Fubin; Dong, Xiaorui; Zhang, Hongguang; Wang, Zhen; Yang, Kai; Zhang, Jian; Wang, Enhua; Liu, Hao; Zhao, Guangyao

    2014-01-01

    Highlights: • Dual loop ORC system is designed to recover waste heat from a diesel engine. • R245fa is used as working fluid for the dual loop ORC system. • Waste heat characteristic under engine various operating conditions is analyzed. • Performance of the combined system under various operating conditions is studied. • The waste heat from coolant and intake air has considerable potential for recovery. - Abstract: To take full advantage of the waste heat from a diesel engine, a set of dual loop organic Rankine cycle (ORC) system is designed to recover exhaust energy, waste heat from the coolant system, and released heat from turbocharged air in the intercooler of a six-cylinder diesel engine. The dual loop ORC system consists of a high temperature loop ORC system and a low temperature loop ORC system. R245fa is selected as the working fluid for both loops. Through the engine test, based on the first and second laws of thermodynamics, the performance of the dual loop ORC system for waste heat recovery is discussed based on the analysis of its waste heat characteristics under engine various operating conditions. Subsequently, the diesel engine-dual loop ORC combined system is presented, and the effective thermal efficiency and the brake specific fuel consumption (BSFC) are chosen to evaluate the operating performances of the diesel engine-dual loop ORC combined system. The results show that, the maximum waste heat recovery efficiency (WHRE) of the dual loop ORC system can reach 5.4% under engine various operating conditions. At the engine rated condition, the dual loop ORC system achieves the largest net power output at 27.85 kW. Compared with the diesel engine, the thermal efficiency of the combined system can be increased by 13%. When the diesel engine is operating at the high load region, the BSFC can be reduced by a maximum 4%

  19. Study of the ideal vitrification conditions of sodium containing waste after oxidation on a fluidized bed

    Petitfour, B.; Rahier, A.

    1997-08-01

    The Belgian Nuclear Research Centre SCK-CEN has patented a new process for the treatment of metallic sodium. This process is fully integrated since it allows to vitrify easily the mixture resulting from the oxidation step. To ensure the link between the treatment and the conditioning, the vitrification conditions have been studied. It is confirmed that an adequate control of the temperature decrease during the vitrification is essential to obtain a product whose area is well known and controlled. Also, the release of Cs and Co has been examined through leaching tests. The study has led to the choice of adequate composition ranges for SiO 2 , Na 2 O, Al 2 O 3 , B 2 O 3 and CaO. Further studies will be carried out to assess the possible use of vitro-crystalline materials for long term conditioning. vitro-crystalline materials for long term conditioning

  20. Thermodynamic modelling and performance study of an engine waste heat driven adsorption cooling for automotive air-conditioning

    Ali, Syed Muztuza; Chakraborty, Anutosh

    2015-01-01

    Waste heat from engine can be utilized to drive an adsorption cooling system for air conditioning purposes in the vehicle cabin, which not only improves the fuel economy but also reduces the carbon footprint. It is also important to reduce the size of the adsorption bed to adopt the adsorption technology for air-conditioning applications in passenger cars, buses and trucks or even trains. In this article, we present a two stage indirect exhaust heat recovery system of automotive engine employing an effective lumped parameter model to simulate the dynamic behaviors of an adsorption chiller that ranges from the transient to the cyclic steady states. The thermodynamic framework of adsorption chiller is developed from the rigor of mass and energy balances of each component of the system and experimentally confirmed isotherms and kinetics data of various adsorbent–adsorbate pairs. The performance factors are calculated in terms of COP (Coefficient of Performance) and SCP (Specific Cooling Power) for different operating parameters such as cycle time, exhaust gas temperatures, cooling water temperatures and flow rates. From the simulation results, it is found that the exhaust energy of a six cylinder 3000 cc private car is able to produce nearly 3 kW of cooling power for the car cabin. It is also observed that the driving heat source temperature does not remain constant throughout the cycle time unlike the conventional adsorption chiller, and the hot water temperatures as driving source vary from 65 to 95 °C. CaCl 2 -in-silica gel–water system is found better in terms of COP and SCP as compared with other adsorbents – water systems. - Highlights: • Adsorption cooling for car air conditioning. • Thermodynamic frameworks with adsorption isotherms and kinetics. • Various adsorbents such as silica gel, zeolites (AQSOA-Z01, Z-02), CaCl 2 -in-silica gel are tested. • Cooling power for car cabin employing waste heat recovery.

  1. Structure study and properties of rare earth-rich glassed for the conditioning of nuclear waste

    Bardez, I.

    2004-11-01

    A new nuclear glass composition, able to immobilize highly radioactive liquid wastes from high burn-up UO 2 fuel, was established and its structure studied. The composition of the selected rare earth-rich glass is (molar %): 61.79 SiO 2 - 8.94 B 2 O 3 - 3.05 Al 2 O 3 - 14.41 Na 2 O - 6.32 CaO - 1.89 ZrO 2 - 3.60 RE 2 O 3 (with RE = La, Ce, Pr and Nd) The aim of this study was to determine the local environment of the rare earth in this glass and also to glean information about the effect of glass composition on the rare earth neighbouring (influence of Si, B, Al, Na and Ca contents). To this end, several series of glasses, prepared from the baseline glass, were studied by different characterisation methods such as EXAFS spectroscopy at the neodymium L III -edge, optical absorption spectroscopy, Raman spectroscopy and 29 Si, 27 Al and 11 B MAS-NMR. By coupling all the results obtained, several hypotheses about the nature of the rare earth neighbouring in the glass were proposed. (author)

  2. Hydrogen absorption of titanium for nuclear waste container in non-oxidizing condition

    Tomari, H.; Masugata, T.; Shimogori, K.; Nishimura, T.; Wada, R.; Honda, A.; Taniguchi, N.

    1999-10-01

    Effects of bentonite clay, applied potential, pH, of solution and cathodic polarization time on hydrogen absorption into titanium, which is one of the candidate materials of overpack for high-level radioactive waste container, have been investigated in artificial underground water. Considering the result at various test time and assuming the hydrogen absorption is ruled by the parabolic law, the amount of hydrogen after 1000 years exposure calculated to about 17ppm, which will be absorbed at the applied potential if -0.51 vs. SHE corresponds to equilibrium potential of hydrogen. It seems the assumption of the parabolic law and the test period are proper, because the linear relations were obtained between the amount of absorbed hydrogen and the logarithm of the averaged cathodic current and between the slopes of the lines and a square root of the test time. Titanium seems to have a life over 1000 years in deep underground repository according to assumption that about 500ppm absorbed hydrogen is critical for hydrogen embrittlement of titanium. (author)

  3. Conditioning of cladding waste by press compaction and encapsulation in low-melting metal alloys

    Broothaerts, J.; Casteels, F.; Daniels, A.; De Regge, P.; Huys, D.; Leurs, A.

    1985-01-01

    The wetting of waste components by lead- and zinc-based alloys has been examined. The lead-based metals, either low or high alloyed, did not achieve acceptable wetting of fresh or oxidized zircaloy surfaces in the temperature range of 350 0 C to 550 0 C for exposure times up to 5 hours. The corrosion resistance of candidate embedment alloys on the basis of lead and zinc has been examined in two synthetic interstitial clay-waters, in direct contact with the clay, in a synthetic Asse brine solution and in contact with wet salt deposits. A unit compaction and embedment of active hulls at the scale of 50 to 100 g has been constructed and installed in a shielded cell. The compaction of irradiated hulls necessitates the use of slightly higher pressures to achieve the densification factor reached for inactive zircaloy. Batches of zircaloy and of stainless steel hulls have been compacted and embedded in lead alloys for leaching experiments using the natural water present in the Boom clay geological formation. A 3 meganewton compaction press has been installed in a mock-up shielded facility and its operation and maintenance by remote handling with telemanipulators has been studied

  4. An HVAC [heating, ventilation, and air-conditioning] fault-tree analysis for WIPP [Waste Isolation Pilot Plant] integrated risk assessment

    Kirby, P.N.; Iacovino, J.M.

    1990-01-01

    In order to evaluate the public health risk of potential radioactive releases from operation of the Waste Isolation Pilot Plant (WIPP), a probabilistic risk assessment of waste-handling operations was conducted. One major aspect of this risk assessment involved fault-tree analysis of the plant heating, ventilation, and air-conditioning (HVAC) systems, which constitute the final barrier between waste-handling operations and the environment. The WIPP site is designed to receive and store two types of waste: contact-handled transuranic (CH TRU) wastes to be shipped in 208-ell drums and remote-handled (RH) TRU wastes to be shipped in shielded casks. The identification of accident sequences for CH waste operations revealed no identified accidents that could release significant radioactive particulates to the environment without a failure in the HVAC systems. When the HVAC fault-tree results were combined with other critical system fault trees and the analysis of waste-handling accident sequences, the approximation of the overall WIPP plant risk due to airborne releases was determined to be 2.6 x 10 -7 fatalities per year for the population within a 50-mile radius of the WIPP site. This risk was demonstrated to be well below the risk of fatality from other voluntary and involuntary activities for the population within the vicinity of the WIPP

  5. Assessments of conditioned radioactive waste arisings from existing and committed nuclear installations and assuming a moderate growth in nuclear electricity generation - June 1985

    Fairclough, M.P.; Goodill, D.R.; Tymons, B.J.

    1985-03-01

    This report describes an assessment of conditioned radioactive waste arisings from existing and committed nuclear installations, DOE Revised Scheme 1, and from an assumed nuclear power generation scenario, DOE Revised Scheme 3, representing a moderate growth in nuclear generation. Radioactive waste arise from 3 main groups of installations and activities: i. existing and committed commercial reactors; ii. fuel reprocessing plants, iii. research, industrial and medical activities. Stage 2 decommissioning wastes are considered together with WAGR decommissioning and the 1983 Sea Dump Consignment. The study uses the SIMULATION 2 code which models waste material flows through a system of waste treatment and packaging to disposal. With a knowledge of the accumulations and average production rates of untreated wastes and their isotopic compositions (or total activities), the rates at which conditioned wastes become available for transportation and disposal are calculated, with specific activity levels. The data for the inventory calculations have previously been documented. Some recent revisions and assumptions concerning future operation of nuclear facilities are presented in this report. (author)

  6. Treatment of waste salt from the advanced spent fuel conditioning process (I): characterization of Zeolite A in Molten LiCl Salt

    Kim, Jeong Guk; Lee, Jae Hee; Yoo, Jae Hyung; Kim, Joon Hyung

    2004-01-01

    The oxide fuel reduction process based on the electrochemical method (Advanced spent fuel Conditioning Process; ACP) and the long-lived radioactive nuclides partitioning process based on electro-refining process, which are being developed ay the Korea Atomic Energy Research Institute (KAERI), are to generate two types of molten salt wastes such as LiCl salt and LiCl-KCl eutectic salt, respectively. These waste salts must meet some criteria for disposal. A conditioning process for LiCl salt waste from ACP has been developed using zeolite A. This treatment process of waste salt using zeolite A was first developed by US ANL (Argonne National Laboratory) for LiCl-KCl eutectic salt waste from an electro-refining process of EBR (Experimental Breeder Reactor)-II spent fuel. This process has been developed recently, and a ceramic waste form (CWF) is produced in demonstration-scale V-mixer (50 kg/batch). However, ANL process is different from KAERI treatment process in waste salt, the former is LiCl-KCl eutectic salt and the latter is LiCl salt. Because of melting point, the immobilization of eutectic salt is carried out at about 770 K, whereas LiCl salt at around 920 K. Such difference has an effect on properties of immobilization media, zeolite A. Here, zeolite A in high-temperature (923 K) molten LiCl salt was characterized by XRD, Ion-exchange, etc., and evaluated if a promising media or not

  7. Crevice corrosion and hydrogen embrittlement of grades-2 and -12 titanium under Canadian nuclear waste vault conditions

    Ikeda, B.M.; Bailey, M.G.; Clarke, C.F.; Shoesmith, D.W.

    1990-01-01

    Results on the corrosion of titanium grades 2 and 12 under the saline conditions anticipated in Canadian nuclear waste vaults are presented. The experimental approach included short-term electrochemical experiments to determine corrosion mechanisms, the susceptibility of titanium to crevice corrosion under a variety of conditions, and the extent of hydrogen uptake under controlled conditions; medium-term corrosion tests lasting a few weeks to a few months; and long-term immersion tests to provide rates for uniform corrosion, crevice corrosion, and hydrogen pickup. Results indicated that propagation, not initiation, is important in establishing susceptibility to crevice corrosion. Increasing the iron content of Ti-2 to 0.13 weight percent prevents crevice corrosion by causing repassivation. Crevice corrosion initiates on Ti-12, but repassivation is rapid. The supply of oxidant is essential to maintain crevice propagation. Hydrogen embrittlement is unlikely unless oxide film breakdown occurs. Film breakdown occurs under crevice conditions, and hydrogen pickup is to be expected. Film breakdown could occur if the strain or creep rate is fast enough to compete with repassivation reactions, a highly unlikely situation

  8. Conditioning of low level radioactive wastes, spent radiation sources and their transport at the interim storage building of the Institute of Nuclear Physics in Albania

    Qafmolla, L.

    2000-01-01

    Aspects of treatment and management of radioactive wastes resulting from the use of radiation sources and radioisotopes in research, medicine and industry, are described. The methods applied for the conditioning of low-level radioactive wastes and spent radiation sources are simple. Solid radioactive wastes with low-level activity, after accumulation, minimization, segregation and measurement, are burned or compressed in a simple compactor of the PGS type. Spent radiation sources are placed into 200 l drums, are cemented and conditioned. Conditioned drums from the Radiation Protection Division of the Institute of Nuclear Physics (INP), which is the responsible Institution for the treatment and management of radioactive wastes in Albania, are transported to the interim storage building of the Institute of Nuclear Physics in Tirana. Work to construct a new building for treatment and management of radioactive wastes and spent radiation sources within the territory of INP is underway. Funds have been allocated accordingly: based on the Law No. 8025 of 25.11.1995, it is the Albanian Government's responsibility to finance activities concerned with the treatment and management of radioactive wastes generating from the use of ionizing radiation in science, medicine and industry in the country. (author)

  9. The thorium phosphate diphosphate as matrix for radioactive waste conditioning: radionuclide immobilization and behavior under irradiation

    Pichot, Erwan

    1999-01-01

    The aim of this work was to perform successively the decontamination of liquid solutions and the final immobilization of radionuclide storage using the same matrix. For this, thorium phosphate-diphosphate (TPD) of the formula Th 4 P 6 O 23 , is proposed as a very resistant to water corrosion matrix. A new compound, thorium phosphate hydrogeno-phosphate (TPHP) of the formula Th 2 (PO 4 ) 2 (HPO 4 ), nH 2 O with n=3-7 was synthesized and characterized. Heated at 1100 deg.C it is transformed into the TDP. Ion exchange properties of TPHP were investigated. The exchange yields of imponderable caesium, strontium and americium ion onto TPHP (NaNO 3 0.1 M media at pH=6) are equal to 60% for the first one and 100% for the two others. The results interpreted in terms of ion-exchange led to determine selectivity coefficient values for each cation and suggested that only hydrated ions are exchanged. While the TPD is proposed for the high level nuclear waste storage, the irradiation effects, particularly structural modifications were studied using both γ irradiation and charged particle irradiation. ESR and TL methods were carried out in order to identify radicals created during gamma radiation exposure. Correlation between ESR and TL experiments performed at room temperature clearly show three of PO 3 2- species and one POO· species of free radicals. We have shown that Au-ion irradiation in the range of MeV energy involved TPD structure and chemical modifications. Important sputtering was interpreted in terms of local thermal chemical decomposition. We have shown, at room temperature, that the amorphization dose for heavy ion irradiation is between 0.1 to 0.4 dpa. (author)

  10. Granular avalanches on the Moon: Mass-wasting conditions, processes, and features

    Kokelaar, B. P.; Bahia, R. S.; Joy, K. H.; Viroulet, S.; Gray, J. M. N. T.

    2017-09-01

    Seven lunar crater sites of granular avalanches are studied utilizing high-resolution images (0.42-1.3 m/pixel) from the Lunar Reconnaissance Orbiter Camera; one, in Kepler crater, is examined in detail. All the sites are slopes of debris extensively aggraded by frictional freezing at their dynamic angle of repose, four in craters formed in basaltic mare and three in the anorthositic highlands. Diverse styles of mass wasting occur, and three types of dry-debris flow deposit are recognized: (1) multiple channel-and-lobe type, with coarse-grained levees and lobate terminations that impound finer debris, (2) single-surge polylobate type, with subparallel arrays of lobes and fingers with segregated coarse-grained margins, and (3) multiple-ribbon type, with tracks reflecting reworked substrate, minor levees, and no coarse terminations. The latter type results from propagation of granular erosion-deposition waves down slopes dominantly of fine regolith, and it is the first recognized natural example. Dimensions, architectures, and granular segregation styles of the two coarse-grained deposit types are like those formed in natural and experimental avalanches on Earth, although the timescale of motion differs due to the reduced gravity. Influences of reduced gravity and fine-grained regolith on dynamics of granular flow and deposition appear slight, but we distinguish, for the first time, extensive remobilization of coarse talus by inundation with finer debris. The (few) sites show no clear difference attributable to the contrasting mare basalt and highland megaregolith host rocks and their fragmentation. This lunar study offers a benchmarking of deposit types that can be attributed to formation without influence of liquid or gas.

  11. NEARSOL - a simple program to model actinide speciation and solubility under waste disposal conditions

    Leach, S.J.; Pryke, D.C.

    1986-05-01

    A simple program, NearSol, has been written in Fortran 77 on the Harwell Central Computer to model the aqueous speciation and solubility of actinides under near-field conditions for disposal using a simple thermodynamic approach. The methodology and running of the program are described together with a worked example. (author)

  12. Metal complexation in near field conditions of nuclear waste repository - stability constant of copper complexation with cellulose degradation products, in alkaline conditions

    Guede, Kipre Bertin

    2005-11-01

    Copper is a stable element and spent fuel component which constitutes the radioactive waste. The reaction of Copper with cellulose degradation products in alkaline conditions was performed to mimic what occurs in near field conditions of nuclear waste repository. From the characteristics of Cu (II), this thesis aims at inferring the behaviour of radionuclides vis a vis the degradation products of cellulose. The contribution of the present work is therefore the assessment of the stability of the major cellulose degradation product, its affinity for Copper and the extent of the complexation function 13 between Cu (II) and the organic moieties. The formation of cellulose degradation products was followed by measurement of p11, Conductivity, Angle of rotation, relative abundance of aliphatics and aromatics (E4/E6 ) aid by UV-visible spectroscopy. The TOC was determined using the Walkley and Black titration after respectively 31 weeks and 13 weeks of degradation for the reaction mixtures T and A, N. The stability of the major degradation products gave the following figures: ISA(A): - 13 43.39 <ΔG -10639.88 ISA(N): - Ii 436.45<ΔG< -9103.6. The study of the characteristics of Gluconic Acid, as a model compound, was carried out in an attempt to give a general picture of the roper ties of cellulose degradation products. The Complexation between Cu (II) and the organic ligand (Cellulose degradation products) was performed using UV-visible spectroscopy and Ion Distribution technique. The Log B value obtained from the complexation studies at 336 nm for 1 = 0. I Ni NaClO4 and I = 0.01 M NaClO4, falls within a range of 3.48 to 3.74 for the standard reference material (Gluconic Acid), and within I .87 to 2.3 I, and I .6 to 2.01, respectively for the degradation Products ISA (A) and ISA(N). The ion distribution studies showed that: • In (he absence of the degradation product ISA and at pH = 3.68. 56. 17 % of Cu (II) was bound to the resin. • In the presence of ISA and at 2

  13. Effects of long-term exposure of tuffs to high-level nuclear waste-repository conditions. Preliminary report

    Blacic, J.; Carter, J.; Halleck, P.; Johnson, P.; Shankland, T.; Andersen, R.; Spicochi, K.; Heller, A.

    1982-02-01

    Tests have been performed to explore the effects of extended exposure of tuffs from the southwestern portion of the Nevada Test Site to temperatures and pressures similar to those that will be encountered in a high-level nuclear waste repository. Tuff samples ranging from highly welded, nonzeolitized to unwelded, highly zeolitized varieties were subjected to temperatures of 80, 120, and 180 0 C; confining pressures of 9.7 and 19.7 MPa; and water-pore pressures of 0.5 to 19.7 MPa for durations of 2 to 6 months. The following basic properties were measured before and after exposure and compared: tensile strength, uniaxial compressive strength, grain density, porosity, mineralogy, permeability, thermal expansion, and thermal conductivity. Depending on rock type and exposure conditions, significant changes in ambient tensile strength, compressive strength, grain density, and porosity were measured. Mineralogic examination, permeability, and thermal property measurements remain to be completed

  14. Site investigation methods used in Canada's nuclear fuel waste management program to determine the hydrogeological conditions of plutonic rock

    Davison, C.C.

    1985-01-01

    Atomic Energy of Canada Limited (AECL) is investigating the concept of disposing of Canada's nuclear fuel wastes in a mined vault at a depth of 500 m to 1000 m within a plutonic rock body. Much effort has been directed at developing site investigation methods that can be used to determine the hydrogeological conditions of plutonic rock bodies. The primary objective of this research is to define the physical and chemical characteristics of groundwater flow systems at the various scales that are relevant to the prediction of potential radionuclide migration from a disposal vault. Groundwater movement through plutonic rock is largely controlled by fractures within the rock, and the hydrogeological parameters of fractured geological media are extremely scale dependent

  15. Long-term degradation of organic polymers under conditions found in deep repositories for low and intermediate-level wastes

    Warthmann, R.; Mosberger, L.; Baier, U.

    2013-06-01

    On behalf of Nagra, the Environmental Biotechnology Section of the Zürich University of Applied Sciences in Wädenswil investigated the potential for microbiological degradation of organic polymers under the conditions found in a deep geological repository for low- and intermediate-level waste (L/ILW). The existing scientific literature on the topic was analysed, some thermodynamic calculations carried out and input was elicited from internationally recognised experts in the field. The study was restricted to a few substances which, in terms of mass, are most significant in the Swiss L/ILW inventory; these are polystyrene (PS), polyvinyl chloride (PVC), other plastics and bitumen. There were no clear indications in the literature that the polymer structure of synthetic polymers is biodegraded under anoxic conditions. However, functional groups of ion exchangers and plasticizers in plastics are considered to be readily available and biodegradable. The greatest obstacle to biological degradation of synthetic polymers is depolymerisation to produce labile monomers. As energy is generally required for such breakdown, the chances of this process taking place outside the cells are very low. In so far as they are present, monomers are, in principle, anaerobically biodegradable. Thermodynamic considerations indicate that degradation of synthetic polymers under repository conditions is theoretically possible. However, the degradation of polystyrene is very close to thermodynamic equilibrium and the usable energy for microorganisms would barely be sufficient. Under high H2 partial pressures, it is predicted that there will be a thermodynamic inhibition of anaerobic degradation, as certain interim steps in degradation are endergonic. The starting conditions for microbial growth in a deep repository are unfavourable in terms of availability of water and prevailing pH values. Practically no known microorganisms can tolerate the combination of these conditions; most known

  16. Subsurface conditions description for the S-SX waste management area

    WOOD, M.I.

    1999-01-01

    This document provides a discussion of the subsurface conditions relevant to the occurrence and migration of contaminants in the vadose zone and groundwater underlying the 241-5 and 241-SX tank farms This document provides a concise summary of existing information in support of characterization planning This document includes a description of the available environmental contamination data and a limited qualitative interpretation of these data

  17. Subsurface Conditions Description of the B and BX and BY Waste Management Area

    WOOD, M.I.

    2000-03-13

    This document provides a discussion of the subsurface conditions relevant to the occurrence and migration of contaminants in the vadose zone and groundwater underlying the 241-B, -BX, and -BY tank farms. This document provides a concise summary of existing information in support of characterization planning. This document includes a description of the available environmental contamination data and a limited, qualitative interpretation of these data.

  18. Beta?hydroxy?beta?methylbutyrate supplementation and skeletal muscle in healthy and muscle?wasting conditions

    Hole?ek, Milan

    2017-01-01

    Abstract Beta?hydroxy?beta?methylbutyrate (HMB) is a metabolite of the essential amino acid leucine that has been reported to have anabolic effects on protein metabolism. The aims of this article were to summarize the results of studies of the effects of HMB on skeletal muscle and to examine the evidence for the rationale to use HMB as a nutritional supplement to exert beneficial effects on muscle mass and function in various conditions of health and disease. The data presented here indicate ...

  19. Subsurface Conditions Description of the B and BX and BY Waste Management Area

    WOOD, M.I.

    2000-01-01

    This document provides a discussion of the subsurface conditions relevant to the occurrence and migration of contaminants in the vadose zone and groundwater underlying the 241-B, -BX, and -BY tank farms. This document provides a concise summary of existing information in support of characterization planning. This document includes a description of the available environmental contamination data and a limited, qualitative interpretation of these data

  20. A novel conditioning process for enhancing dewaterability of waste activated sludge by combination of zero-valent iron and persulfate.

    Zhou, Xu; Wang, Qilin; Jiang, Guangming; Liu, Peng; Yuan, Zhiguo

    2015-06-01

    Improvement of sludge dewaterability is crucial for reducing the costs of sludge disposal in wastewater treatment plants. This study presents a novel conditioning method for improving waste activated sludge dewaterability by combination of persulfate and zero-valent iron. The combination of zero-valent iron (0-30g/L) and persulfate (0-6g/L) under neutral pH substantially enhanced the sludge dewaterability due to the advanced oxidization reactions. The highest enhancement of sludge dewaterability was achieved at 4g persulfate/L and 15g zero-valent iron/L, with which the capillary suction time was reduced by over 50%. The release of soluble chemical oxygen demand during the conditioning process implied the decomposition of sludge structure and microorganisms, which facilitated the improvement of dewaterability due to the release of bound water that was included in sludge structure and microorganism. Economic analysis showed that the proposed conditioning process with persulfate and ZVI is more economically favorable for improving WAS dewaterability than classical Fenton reagent. Copyright © 2015 Elsevier Ltd. All rights reserved.

  1. Harmful Waste Process

    Ki, Mun Bong; Lee, Shi Jin; Park, Jun Seok; Yoon, Seok Pyo; Lee, Jae Hyo; Jo, Byeong Ryeol

    2008-08-01

    This book gives descriptions of processing harmful waste, including concerned law and definition of harmful waste, current conditions and generation of harmful waste in Korea, international condition of harmful waste, minimizing of generation of harmful waste, treatment and storage. It also tells of basic science for harmful waste disposal with physics, chemistry, combustion engineering, microbiology and technique of disposal such as physical, chemical, biological process, stabilizing and solidification, incineration and waste in landfill.

  2. Conditions for the test emplacement of intermediate-level radioactive wastes in chamber 8a of the 511 m level of the Asse Salt Mine

    1984-01-01

    The Gesellschaft fuer Strahlen- und Umweltforschung mbH (GSF) emplaces intermediate-level radioactive wastes which accumulate in an activity involving the use of radioactive materials that is licensed or reported in the Federal Republic of Germany or which are stored on an interim basis by the appropriate licensing or inspection agencies in chamber 8a of the 511 m level of the Asse Salt Mine in Remlingen near Wolfenbuettel in conjunction with an engineering test program. The type and form of the intermediate-level wastes must conform to certain conditions so that there are no hazards to personnel and the repository during transfer and subsequent storage. It is therefore necessary for the radioactive wastes to be treated and packaged before delivery in such a way that they satisfy the conditions presented in this document. The GSF shall inform the companies and organizations delivering wastes about its experiences with emplacement operations. The Conditions for the Test Emplacement of Intermediate-Level Radioactive Wastes in Chamber 8a of the 511 m Level of the Asse Salt Mine must be adapted to conform to the latest state of science and the art. The GSF must therefore reserve the right to modify the conditions, allowing for an appropriate transition period

  3. Investigation into the behaviour of highly compacted dry low-level radioactive waste under repository conditions. Task 3 characterization of radioactive waste forms a series of final reports (1985-89) no 12

    Field, S.N.; Wang, J.

    1991-01-01

    Supercompaction is a process in which drums containing low-level radioactive waste are compressed at a high axial pressure of up to 70 MPa, resulting in a significant saving in the volume of a repository built to store such waste. Recent practice of supercompaction is to compact waste which has been placed in a sealed primary container, typically a 200-litre steel drum. During the process of compaction the drum is squashed with its contents into a flat pellet; and the compaction ratio can reach as high as 20:1. Although the compaction of radioactive waste has long been a popular means for reducing its storage volume, there is virtually no available information as to the physical or chemical characteristics of such compacted wastes. The primary objective of this project has been to investigate the physical and some of the chemical characteristics of such supercompacted pellets. All the work was carried out on full-scale 200-litre drums of simulated, but non-radioactive, waste. The compaction ratio reached in this study ranged from 5 to 21, depending on the type of waste. Upon completion of compaction, all drums exhibited a tendency to expand. The magnitude of ultimate expansion for dry storage was of the order of 1 mm only, whereas under wet storage conditions values were up to about 10 mm. As the presence of moisture can significantly increase the expansion of compacted waste drums or stress developed due to restraint, it is recommended that the waste repository be made water/vapour-tight

  4. Simulation of concrete deterioration in Finnish rock cavern conditions for final disposal of nuclear waste

    Kari, O.P.; Puttonen, J.

    2014-01-01

    Highlights: • Concrete deterioration in Finnish rock cavern disposal conditions was simulated. • Simulation requires advanced models instead of traditional linear diffusion models. • Concrete analysed performed moderately during the period of 500 years. • Corrosion of steel reinforcement cannot be excluded during the period analysed. - Abstract: A simulation of concrete ageing in Finnish rock cavern disposal conditions showed that the concrete undergoes complex deterioration processes during the period required for lowering the level of radiation. In respect of the concrete ageing, the life time of the disposal facilities shall be divided into the periods before and after the closing of the caverns. Generally, the sulphate-resistant type of concrete analysed performed moderately during the analysed period of 500 years contrary to the corrosion of steel reinforcement, which cannot be excluded. Simulation of ageing clearly requires thermodynamical methods instead of linear diffusion models based on Fick’s law, which are traditionally used in construction industry. The study proves that the thermodynamical simulation method developed with adequate experimental data also makes it possible to observe latent factors of concrete deterioration

  5. Effects of Degree of Superheat on the Running Performance of an Organic Rankine Cycle (ORC Waste Heat Recovery System for Diesel Engines under Various Operating Conditions

    Kai Yang

    2014-04-01

    Full Text Available This study analyzed the variation law of engine exhaust energy under various operating conditions to improve the thermal efficiency and fuel economy of diesel engines. An organic Rankine cycle (ORC waste heat recovery system with internal heat exchanger (IHE was designed to recover waste heat from the diesel engine exhaust. The zeotropic mixture R416A was used as the working fluid for the ORC. Three evaluation indexes were presented as follows: waste heat recovery efficiency (WHRE, engine thermal efficiency increasing ratio (ETEIR, and output energy density of working fluid (OEDWF. In terms of various operating conditions of the diesel engine, this study investigated the variation tendencies of the running performances of the ORC waste heat recovery system and the effects of the degree of superheat on the running performance of the ORC waste heat recovery system through theoretical calculations. The research findings showed that the net power output, WHRE, and ETEIR of the ORC waste heat recovery system reach their maxima when the degree of superheat is 40 K, engine speed is 2200 r/min, and engine torque is 1200 N·m. OEDWF gradually increases with the increase in the degree of superheat, which indicates that the required mass flow rate of R416A decreases for a certain net power output, thereby significantly decreasing the risk of environmental pollution.

  6. Obsidian: alteration study under hydrothermal-like conditions for its assessment as a nuclear waste glass

    Rania, Nishi; Shrivastava, J.P.; Bajpai, R.K.

    2013-01-01

    Alteration experiments of obsidian (from Osham Hill, Gujarat, India) were performed under hydrothermal-like conditions. Neo-formed minerals were compared with naturally altered minerals to assess its performance. Altered specimens show partial to complete leaching of glass, where ionic release is of the order of Na>Si>K>Ca>Al = Mg>Mn>Ti. SEM-BSE images show distinct microstructures and mineral paragenesis of smectite, chlorite, nontronite, and illite inside and outside of the secondary layers - show retention of Si, Al, and Mg ions, fixation in the alteration products after their meager release to the solution. Secondary minerals-palagonite, chlorite, calcite, zeolite and white colored clays - formed after experiments largely correspond to altered obsidian in the natural environment since ∼ 65 Ma. (authors)

  7. Obsidian: alteration study under hydrothermal-like conditions for its assessment as a nuclear waste glass

    Rania, Nishi; Shrivastava, J.P. [Department of Geology, University of Delhi, Delhi - 110007 (India); Bajpai, R.K. [BETDD, Nuclear Recycle Group, BARC, Mumbai - 400008 (India)

    2013-07-01

    Alteration experiments of obsidian (from Osham Hill, Gujarat, India) were performed under hydrothermal-like conditions. Neo-formed minerals were compared with naturally altered minerals to assess its performance. Altered specimens show partial to complete leaching of glass, where ionic release is of the order of Na>Si>K>Ca>Al = Mg>Mn>Ti. SEM-BSE images show distinct microstructures and mineral paragenesis of smectite, chlorite, nontronite, and illite inside and outside of the secondary layers - show retention of Si, Al, and Mg ions, fixation in the alteration products after their meager release to the solution. Secondary minerals-palagonite, chlorite, calcite, zeolite and white colored clays - formed after experiments largely correspond to altered obsidian in the natural environment since ∼ 65 Ma. (authors)

  8. Geotechnical conditions of Bulgaria and site selection for radioactive waste repository

    Iliev, I.; Tacheva, E.

    1993-01-01

    A comparative study of the complex structure of the Bulgarian lands and the engineering geological criteria for site selection of national repositories for high level radwastes is made. A detailed description of the following geotechnical conditions of Bulgaria's territory is given: genetic, lithological and engineering-geological types of rocks; physico-mechanical parameters of the most widespread rocky and semi-rocky engineering geological types; fissuring of the rocks; rock massifs; geodynamic processes. The number of promising variants for repositories have been classified according to the structure of the rock massif and the engineering-geological properties of the layers which are promising for the purpose. The following sites are investigated: 1) sites in one-type homogeneous rock massifs of high strength and elasticity; 2) sites of various type massifs with a promising layer of rocks with medium strength and elasticity; 3) sites in various type massifs with a promising layer of plastic rocks of low strength. It is concluded that the complexity of the geotechnical and other conditions in the territory of Bulgaria would predetermine the deficiency of the list of the properties required for the selected sites. The building up of engineering defence will be needed to offset that deficiency and their problems will be resolved after the specific site have been chosen. Geotechnical elements should be likewise envisaged within the general pattern of the monitoring needed. The designing, installing and putting into operation of the monitoring systems should be accomplished as early as the stage of the detailed investigation of the site selected. 19 refs., 2 suppls. (author)

  9. Long term behaviour of low and intermediate level waste packages under repository conditions. Results of a co-ordinated research project 1997-2002

    2004-06-01

    The development and application of approaches and technologies that provide long term safety is an essential issue in the disposal of radioactive waste. For low and intermediate level radioactive waste, engineered barriers play an important role in the overall safety and performance of near surface repositories. Thus, developing a strong technical basis for understanding the behaviour and performance of engineered barriers is an important consideration in the development and establishment of near surface repositories for radioactive waste. In 1993, a Co-ordinated Research Project (CRP) on Performance of Engineered Barrier Materials in Near Surface Disposal Facilities for Radioactive Waste was initiated by the IAEA with the twin goals of addressing some of the gaps in the database on radionuclide isolation and long term performance of a wide variety of materials and components that constitute the engineered barriers system (IAEA-TECDOC-1255 (2001)). However, during the course of the CRP, it was realized that that the scope of the CRP did not include studies of the behaviour of waste packages over time. Given that a waste package represents an important component of the overall near surface disposal system and the fact that many Member States have active R and D programmes related to waste package testing and evaluation, a new CRP was launched, in 1997, on Long Term Behaviour of Low and Intermediate Level Waste Packages Under Repository Conditions. The CRP was intended to promote research activities on the subject area in Member States, share information on the topic among the participating countries, and contribute to advancing technologies for near surface disposal of radioactive waste. Thus, this CRP complements the afore mentioned CRP on studies of engineered barriers. With the active participation and valuable contributions from twenty scientists and engineers from Argentina, Canada, Czech Republic, Egypt, Finland, India, Republic of Korea, Norway, Romania

  10. Chemical reactivity of precursor materials during synthesis of glasses used for conditioning high-level radioactive waste: Experiments and models

    Monteiro, A.

    2012-01-01

    The glass used to store high-level radioactive waste is produced by reaction of a solid waste residue and a glassy precursor (glass frit). The waste residue is first dried and calcined (to lose water and nitrogen respectively), then mixed with the glass frit to enable vitrification at high temperature. In order to obtain a good quality glass of constant composition upon cooling, the chemical reactions between the solid precursors must be complete while in the liquid state, to enable incorporation of the radioactive elements into the glassy matrix. The physical and chemical conditions during glass synthesis (e.g. temperature, relative proportions of frit and calcine, amount of radioactive charge) are typically empirically adjusted to obtain a satisfactory final product. The aim of this work is to provide new insights into the chemical and physical interactions that take place during vitrification and to provide data for a mathematical model that has been developed to simulate the chemical reactions. The consequences of the different chemical reactions that involve solid, liquid and gaseous phases are described (thermal effects, changes in crystal morphology and composition, variations in melt properties and structure). In a first series of experiments, a simplified analogue of the calcine (NaNO 3 -Al 2 O 3 ± MoO 3 /Nd 2 O 3 ) has been studied. In a second series of experiments, the simplified calcines have been reacted with a simplified glass frit (SiO 2 -Na 2 O-B 2 O 3 -Al 2 O 3 ) at high temperature. The results show that crystallization of the calcine may take place before interaction with the glass frit, but that the reactivity with the glass at high temperature is a function of the nature and stoichiometry of the crystalline phases which form at low temperature. The results also highlight how the mixing of the starting materials, the physical properties of the frit (viscosity, glass transition temperature) and the Na 2 O/Al 2 O 3 of the calcine but also its

  11. Partitioning of Tank Waste Sludge in a 5-cm Centrifugal Contactor Under Caustic-Side Solvent Extraction Conditions

    Birdwell, Jr. J.F.

    2001-01-01

    A test program has been performed to evaluate the effect of solids on the hydraulic performance of a 5-cm centrifugal contactor under conditions present in the extraction section of the Caustic-Side Solvent Extraction (CSSX) process. In addition to determining if the ability to separate the aqueous and organic phases is affected by the presence of solids in a feed solution, the extent to which solids are accumulated in the contactor was also assessed. The reported task was motivated by the need to determine if removal of cesium from Savannah River Site tank waste can be performed using a contactor-based CSSX process without first removing sludge that is suspended in the feed solution. The ability to pass solids through the CSSX process could facilitate placement of CSSX upstream of a process in which alpha-decaying actinides and strontium are removed from the waste stream by precipitation with monosodium titanate (MST). This relative placement of the CSSX and MST processes is desirable because removal of cesium would greatly reduce the activity level of the feed stream to the MST process, thereby reducing the level of shielding needed and mitigating remote maintenance design features of MST equipment. Both results would significantly reduce the cost of the Salt Processing Project. Test results indicate conclusively that a large fraction of suspended sludge that enters the centrifugal contactor remains inside. It is expected that extended operation would result in continued accumulation of solids and that hydraulic performance would be adversely affected. Results also indicate that a fraction of the solids partitions to the phase boundary and could affect phase separation as contactor operations progress

  12. Electrochemical pretreatment of waste activated sludge: effect of process conditions on sludge disintegration degree and methane production.

    Ye, Caihong; Yuan, Haiping; Dai, Xiaohu; Lou, Ziyang; Zhu, Nanwen

    2016-11-01

    Waste activated sludge (WAS) requires a long digestion time because of a rate-limiting hydrolysis step - the first phase of anaerobic digestion (AD). Pretreatment can be used prior to AD to facilitate the hydrolysis step and improve the efficiency of WAS digestion. This study evaluated a novel application of electrochemical (EC) technology employed as the pretreatment method prior to AD of WAS, focusing on the effect of process conditions on sludge disintegration and subsequent AD process. A superior process condition of EC pretreatment was obtained by reaction time of 30 min, electrolysis voltage of 20 V, and electrode distance of 5 cm, under which the disintegration degree of WAS ranged between 9.02% and 9.72%. In the subsequent batch AD tests, 206 mL/g volatile solid (VS) methane production in EC pretreated sludge was obtained, which was 20.47% higher than that of unpretreated sludge. The AD time was 19 days shorter for EC pretreated sludge compared to the unpretreated sludge. Additionally, the EC + AD reactor achieved 41.84% of VS removal at the end of AD. The analysis of energy consumption showed that EC pretreatment could be effective in enhancing sludge AD with reduced energy consumption when compared to other pretreatment methods.

  13. Differential fate of erythromycin and beta-lactam resistance genes from swine lagoon waste under different aquatic conditions

    Knapp, Charles W., E-mail: charles.knapp@strath.ac.u [David Livingstone Centre for Sustainability, Department of Civil Engineering, University of Strathclyde, 50 Richmond Street, Glasgow, G1 1XN (United Kingdom); School of Civil Engineering and Geosciences, Newcastle University, Newcastle upon Tyne, NE1 7RU (United Kingdom); Zhang, Wen; Sturm, Belinda S.M. [Department of Civil, Environmental and Architectural Engineering, University of Kansas, Lawrence, KS 66045 (United States); Graham, David W. [School of Civil Engineering and Geosciences, Newcastle University, Newcastle upon Tyne, NE1 7RU (United Kingdom); Department of Civil, Environmental and Architectural Engineering, University of Kansas, Lawrence, KS 66045 (United States)

    2010-05-15

    The attenuation and fate of erythromycin-resistance-methylase (erm) and extended-spectrum beta-lactamse (bla) genes were quantified over time in aquatic systems by adding 20-L swine waste to 11,300-L outdoor mesocosms that simulated receiving water conditions below intensive agricultural operations. The units were prepared with two different light-exposure scenarios and included artificial substrates to assess gene movement into biofilms. Of eleven genes tested, only erm(B), erm(F), bla{sub SHV} and bla{sub TEM} were found in sufficient quantity for monitoring. The genes disappeared rapidly from the water column and first-order water-column disappearance coefficients were calculated. However, detected gene levels became elevated in the biofilms within 2 days, but then disappeared over time. Differences were observed between sunlight and dark treatments and among individual genes, suggesting that ecological and gene-specific factors play roles in the fate of these genes after release into the environment. Ultimately, this information will aid in generating better predictive models for gene fate. - The disappearance and fate of erythromycin-resistance-methylase and beta-lactamase genes were monitored in outdoor mesocosms under different light conditions.

  14. In situ corrosion studies on selected high level waste packaging materials under simulated disposal conditions in rock salt

    Smailos, E.; Schwarzkopf, W.; Koester, R.

    1988-01-01

    In order to qualify corrosion resistant materials for high level waste (HLW) packagings acting as a long-term barrier in a rock salt repository, the corrosion behavior of preselected materials is being investigated in laboratory-scale and in-situ experiments. This work reports about in-situ corrosion experiments on unalloyed steels, Ti 99.8-Pd, Hastelloy C4, and iron-base alloys, as nodular cast iron, Ni-Resist D4 and Si-cast iron, under simulated disposal conditions. The results of the investigations can be summarized as follows: (1) all materials investigated exhibited high resistance to corrosion under the conditions prevailing in the Brine Migration Test; (2) all materials and above all the materials with passivating oxide layers such as Ti 99.8-Pd and Hastelloy C4 which may corrode selectively already in the presence of minor amounts of brine had been resistant with respect to any type of local corrosion attack; the gamma-radiation of 3 · 10 2 Gy/h did not exert an influence on the corrosion behavior of the materials

  15. Assessment of radiation doses in normal operation, upset accident conditions at the Olkiluoto nuclear waste facility

    Rossi, J.; Raiko, H.; Suolanen, V.

    2009-09-01

    Radiation doses for workers of the facility, for inhabitants in the environment and for terrestrial ecosystem possibly caused by the encapsulation and disposal facility to be built at Olkiluoto during its operation were considered in the study. The study covers both the normal operation of the plant and some hypothetical incidents and accidents. Release through the ventilation stack is assumed to be filtered both in normal operation and in hypothetical abnormal fault and accident cases. Calculation of the offsite doses from normal operation is based on the hypothesis that on average one fuel pin per 100 fuel bundles for all batches of spent fuel transported to the encapsulation facility is leaking. The release magnitude in incidents and accidents is based on the event chains, which lead to loss of fuel pin tightness followed by a discharge of radionuclides into the handling space and to some degree to the atmosphere through the ventilation stack equipped with redundant filters. The critical group is conservatively assumed to live at the distance of 200 meters from the encapsulation and disposal plant and thus it will receive the largest doses in most dispersion conditions. The dose value to a member of the critical group was calculated on the basis of the weather data in such a way that greater dose than obtained here is caused only in 0.5 percent of dispersion conditions. The results obtained indicate that during normal operation the doses to workers remain small and the dose to the member of the critical group is less than 0,001 mSv per year. In the case of hypothetical fault and accident releases the offsite doses do not exceed either the limit values set by the safety authority. The highest dose rates to the reference organisms of the terrestrial ecosystem with conservative assumptions from the largest release were estimated to be of the order of 100 μ Gy/h at the distance of 200 m. As a chronic exposure this dose rate is expected to bring up detrimental

  16. Localized corrosion of Alloy C22 nuclear waste canister material under limiting conditions

    Lee, S.G.; Solomon, A.A.

    2006-01-01

    Localized corrosion behavior of Alloy C22 in simulated Yucca Mountain (YM) repository environments was studied at the highest achievable but realistic temperatures under boiling and dripping scenarios. Temperatures measured in concentrated boiling solutions of KCl and NaNO 3 were found to be stable at 140 deg. C, although transient boiling before dryout was observed at temperatures as high as 160 deg. C, as the electrolyte became progressively more concentrated. Experiments that simulated a dripping scenario with simulated J13 well water confirmed the existence of concentrated solutions stable at 142 ± 3 deg. C under controlled drip conditions leading to pit initiation in Alloy C22 after only a few hours. The polarization experiments conducted at 140 deg. C in a solution with 0.5 mol L -1 chloride concentration showed that the critical potential for localized corrosion was 250 mV (versus Ag/AgCl). Potentiostatic tests confirmed that active metal dissolution occurred only in the crevice region at this potential. The crevice corrosion of Alloy C22 required an incubation time to develop a critical crevice solution, and it was triggered by severe local chemistry (enrichment of Cl - and H + ) aided by the high temperature

  17. Nuclear waste shipping container response to severe accident conditions, A brief critique of the modal study

    Audin, L.

    1990-12-01

    The Modal Study (NUREG/CR-4829) attempts to upgrade the analysis of spent nuclear fuel transportation accidents, and to verify the validity of the present regulatory scheme of cask performance standards as a means to minimize risk. While an improvement over many prior efforts in this area (such as NUREG-0170), it unfortunately fails to create a realistic simulation either of a shipping cask, the severe conditions to which it could be subjected, or the potential damage to the spent fuel cargo during an accident. There are too many deficiencies in its analysis to allow acceptance of its results for the presumed cask design, and many pending changes in new containers, cargoes and shipping patterns will limit applicability of the Modal Study to future shipments. In essence, the Modal Study is a good start, but is too simplistic, incomplete, outdated and open to serious question to be used as the basis for any present-day environmental or risk assessment of spent fuel transportation. It needs to be redone, with peer review during its production and experimental verification of its assumptions, before it has any relevance to the shipments planned to Yucca Mountain. Finally, it must be expanded into a full risk assessment by inputing its radiological release fractions and probabilities into a valid dispersal simulation to properly determine the impact of its results. 51 refs

  18. Mixing conditions in application of bentonite grouting to radioactive waste disposal

    Kobayakawa, Hiroaki; Ito, Hiroshi

    2007-01-01

    The purpose of this study was to understand the flow properties and permeability of bentonite grout with NaCl added, using laboratory tests, and to clarify the mixing conditions of bentonite as a material. Given that the required permeability of clay grout is 10 -9 (m/s), the combination of grout (W/B) becomes 6 or less. The viscosity of the grout was measured, and because the viscosity was higher than the thickest cement milk on dam grouting, it was found that grout with a W/B of less than 10 was difficult to inject into rock joints. We then added NaCl to grout with a W/B is 6, and its viscosity decreased as the amount of NaCl increased. A grout of viscosity able to be injected into rock joints was achieved by adding NaCl in a density higher than 'W:NaCl=40:1'. Next, the permeability of a bentonite suspension with NaCl was examined using the falling head permeability test. Testing the sample 'B:W:NaCl=20:20:1' for 10 days revealed that the initial permeability 10 -8 (m/s) decreased to 10 -10 - 10 -11 (m/s). These results showed that a suspension to inject into rock joints could be made by adding NaCl, and clarified that permeation of groundwater into the suspension causes a decline in permeability. (author)

  19. Technical specifications for waste packages conditioned in a durable confining shell, with an hydraulic binder basis, intended to a ground disposal site

    1995-06-01

    The aim of this document is to precise the general and particular conditions for the acceptance on a ground disposal site of a low- and middle-level radioactive waste package conditioned in a durable confining shell. This specification concerns the wastes that contain beta and gamma decay radionuclides and/or long life alpha decay radionuclides in higher quantities than accepted for the protective coatings. Physico-chemical and mechanical specifications are given for the wastes, the fixing material, the confining shell and the container. Accepted limits for degassing and dose rates, surface contamination, dimensions and weight are given. The agreement is delivered by the ANDRA after the package has satisfied the different mechanical, chemical, fire, moisture and radiation resistance tests. (J.S.). 1 fig., 3 tabs., 1 glossary

  20. Osmosis-induced water uptake by Eurobitum bituminized radioactive waste and pressure development in constant volume conditions

    Mariën, A.; Mokni, N.; Valcke, E.; Olivella, S.; Smets, S.; Li, X.

    2013-01-01

    Highlights: ► The water uptake by Eurobitum is studied to judge the safety of geological disposal. ► High pressures of up to 20 MPa are measured in constant volume water uptake tests. ► The morphology of leached Eurobitum samples is studied with μCT and ESEM. ► The observations are reproduced by an existing CHM formulation for Eurobitum. - Abstract: The chemo-hydro-mechanical (CHM) interaction between swelling Eurobitum radioactive bituminized waste (BW) and Boom Clay is investigated to assess the feasibility of geological disposal for the long-term management of this waste. These so-called compatibility studies include laboratory water uptake tests at Belgian Nuclear Research Center SCK-CEN, and the development of a coupled CHM formulation for Eurobitum by the International Center for Numerical Methods and Engineering (CIMNE, Polytechnical University of Cataluña, Spain). In the water uptake tests, the osmosis-induced swelling, pressure increase and NaNO 3 leaching of small cylindrical BW samples (diameter 38 mm, height 10 mm) is studied under constant total stress conditions and nearly constant volume conditions; the actual geological disposal conditions should be intermediate between these extremes. Two nearly constant volume tests were stopped after 1036 and 1555 days to characterize the morphology of the hydrated BW samples and to visualize the hydrated part with microfocus X-ray Computer Tomography (μCT) and Environmental Scanning Electron Microscopy (ESEM). In parallel, a coupled CHM formulation is developed that describes chemically and hydraulically coupled flow processes in porous materials with salt crystals, and that incorporates a porosity dependent membrane efficiency, permeability and diffusivity. When Eurobitum BW is hydrated in (nearly) constant volume conditions, the osmosis-induced water uptake results in an increasing pressure to values that can be (in theory) as high as 42.8 MPa, being the osmotic pressure of a saturated NaNO 3

  1. Experiences gained in the conditioning of radioactive wastes from regional depots by example of Kernforschungszentrum Karlsruhe, and recommendations for the establishment of regional depots in the new Federal States of unified Germany

    Pfeifer, W.

    1992-01-01

    Details are given about radioactive waste management and radioactive waste management fundamentals as well as about the respective methods applied by the Baden-Wuerttemberg radioacive waste depot. The waste treatment, quality assurance and internal inspection methods applied by Hauptabteilung Dekontaminationsbetriebe (HDB), Kernforschungszentrum Karlsruhe (KfK) are described, and recommendations are given for the establishment of regional depots in the new provinces of the Federal Republic of Germany. These recommendations which are based on Western German standards before unification suggest regional depots with combined administrative systems which watch over the depot use and charges, the foundation of a waste management association responsible for the disposal, transport, intermediate storage and conditioning of radioactive wastes in the new provinces, and the establishment of a facility to be run by the proposed waste management association for the intermediate storage of conditioned waste packages intended for final disposal. (orig.) [de

  2. Estimative of alpha radiation dose due to natural concentration of Ra-226 in waters from Pocos de Caldas

    Sigaud, G.M.

    1979-01-01

    A dosimetric model for calculating the annual dose equivalent for an individual and the annual collective dose equivalent from 226 Ra is developed. This model is applied to the measured concentrations of 226 Ra in waters of the hydro graphic basins of the Pocos de Caldas plateau, using the pathways of drinking water and ingestion of food grown in irrigated fields. A linear model for simulating potential 226 Ra contamination of the waters of the region is also applied, and the doses from these contaminations are estimated using the dosimetric model developed. (author)

  3. Applications of PB-210/RA-226 and PO-210/PB-210 disequilibria in the study of marine geochemical processes

    Bacon, M.P.

    1976-02-01

    The distribution of 210 Pb and 210 Po in dissolved (less than 0.4 micron) and particulate (greater than 0.4 micron) phases was measured at ten stations in the tropical and eastern North Atlantic and at two stations in the Pacific. Both radionuclides occur principally in the dissolved phase. Unsupported 210 Pb activities, maintained by flux from the atmosphere, were present in the surface mixed layer and penetrated into the thermocline to depths of about 500 m. Dissolved 210 Po was ordinarily present in the mixed layer at less than equilibrium concentrations, suggesting rapid biological removal of this nuclide. Particulate matter was enriched in 210 Po, with 210 Po/ 210 Pb activity ratios greater than 1.0, similar to those reported for phytoplankton. Box-model calculations yield a 2-y residence time for 210 Pb and a 0.6-y residence time for 210 Po in the mixed layer. These residence times are considerably longer than the time calculated for turnover of particles in the mixed layer (about 0.1 y). At depths of 100 to 300 m, 210 Po maxima occurred and unsupported 210 Po was frequently present. Calculations indicate that at least 50 percent of the 210 Po removed from the mixed layer is re-cycled within the thermocline. Similar calculations for 210 Pb suggest much lower re-cycling efficiencies

  4. Partitioning and redistribution of exogenous Ra226 in farm soils from the vicinity of the First Brazilian Mine and Mill

    Teixeira, V.S.; Franca, E.P.

    1988-01-01

    A sequential selective extration method was employed to assess the partitioning and redistribution of exogenous 226 Ra into geochemical fractions of farm soils collected around the first Brazilian Uranium Mine and Mill. Six soil samples were contaminated in the laboratory by 226 a solution, simulating an irrigation procedure. After selective extractions, 226 Ra was analysed in six geochemical fractions: soluble (A); exchangeable (E); bound to carbonates (C); reducible (R); oxidizable (O); residual or matricial (M). The same method was also used in these soils before and after cultivation. The exogenous 226 Ra was mainly associated to the (R) and (O) fractions followed by the (E) and (C) ones. Exchangeable 226 Ra (fractions (A) + (E)) represents 21.8%. Statistically significant differences before and after cultivation were obtained only in the fractions (C) and (M). (Author) [pt

  5. Measuring the radium quartet (228Ra, 226Ra, 224Ra, 223Ra) in seawater samples using gamma spectrometry

    Beek, P. van; Souhaut, M.; Reyss, J.-L.

    2010-01-01

    Radium isotopes are widely used in marine studies (eg. to trace water masses, to quantify mixing processes or to study submarine groundwater discharge). While 228 Ra and 226 Ra are usually measured using gamma spectrometry, short-lived Ra isotopes ( 224 Ra and 223 Ra) are usually measured using a Radium Delayed Coincidence Counter (RaDeCC). Here we show that the four radium isotopes can be analyzed using gamma spectrometry. We report 226 Ra, 228 Ra, 224 Ra, 223 Ra activities measured using low-background gamma spectrometry in standard samples, in water samples collected in the vicinity of our laboratory (La Palme and Vaccares lagoons, France) but also in seawater samples collected in the plume of the Amazon river, off French Guyana (AMANDES project). The 223 Ra and 224 Ra activities determined in these samples using gamma spectrometry were compared to the activities determined using RaDeCC. Activities determined using the two techniques are in good agreement. Uncertainties associated with the 224 Ra activities are similar for the two techniques. RaDeCC is more sensitive for the detection of low 223 Ra activities. Gamma spectrometry thus constitutes an alternate method for the determination of short-lived Ra isotopes.

  6. Radon fixation for determination of 224Ra, 226Ra and 228Ra via gamma-ray spectrometry

    Herranz, M.; Idoeta, R.; Abelairas, A.; Legarda, F.

    2006-01-01

    The aim of this work is the improvement of the procedure for the determination of radium isotopes activities in water, which is done through radiochemical separation and subsequent gamma-ray spectrometry. In addition, radon gas retention is studied using different activated carbon materials. The results of the IAEA Proficiency test: 'Determination of radium and uranium radionuclides in water' of December 2002 [IAEA, 2003. Analytical quality control services: determination of radium and uranium radionuclides in water. Preliminary Report, Seibersdorf] are considered for this work

  7. Evaluation of the environmental radiological impact of Brazilian phosphogypsum and leachability of Ra-226 and Pb-210

    Santos, Adir Janete Godoy dos

    2002-01-01

    Phosphogypsum is a by-product produced by the phosphoric acid industry, it is formed by precipitation during wet sulphuric acid processing of phosphate rock. Although phosphogypsum is mainly calcium sulphate dihydrate, it contains elevated levels of impurities, which originate from the source phosphate rock used in the phosphoric acid production. Among these impurities, radionuclides from 238 U and 232 Th decay series, particularly 226 Ra, 228 Ra, 210 Pb and Th isotopes are of most concern due to their radiotoxicity. Elemental characterization of stockpiled phosphogypsum from the two main producers of phosphoric acid, Copebras Ltda and Ultrafertil S.A. named A and C respectively, located in Cubatao, was performed by instrumental neutron activation analysis (INAA). Phosphogypsum samples are enriched in rare earths elements, specifically Ce, Eu, La, Nd, Sm, Tb and Yb and the elements Ba and Th. Radiological characterization of stockpiled phosphogypsum was performed by gamma-ray spectrometry. Activity concentrations (2,3 +- 0,5) x 10 2 Bq kg -1 for 228 Ra, (8,5 +- 2,4) x 10 2 Bq kg -1 for 226 Ra and (8,4 +- 2,4) x 10 2 Bq kg -1 for 210 Pb were observed for industry A phosphogypsum. For industry C phosphogypsum, activity concentrations obtained were (1,6 +- 0,6) x 10 2 Bq kg - ''1 for 226 Ra, (3,6 +- 1,2) x 10 2 Bq kg -1 for 226 Ra and (3,4 +- 1,2) x 10 2 Bq kg -1 for 210 Pb. The radiochemical and elemental characterization of the phosphogypsum from industry A and C show that the stacks are quite homogeneous and mainly dependent upon the origin of the phosphatic rock used as raw material. The environmental radiological impact assessment of stockpiled phosphogypsum from industry C was evaluated by taking into account internal and external doses. The critical pathways considered were contamination of groundwater, emanation of radon and direct external exposure due to the radionuclides present in the phosphogypsum. The activity concentrations obtained in the monitor wells water were (1,5 +- 0,6) Bq L -1 for 226 Ra, (6,0 +- 2,4) Bq L -1 for 228 Ra and (2,1 +- 1,0) Bq L -1 for 210 Pb. Activity concentrations obtained for 222 Rn in air varied from (0,8 +- 0,1) x 10 Bq m -3 to (4,8 +- 0,7) x 10 Bq m -3 . No 222 Rn decay products were observed above the detection limit of the equipment (6 x 10 -2 WLM). Higher doses were observed for the ingestion of water, showing that groundwater contamination is the most critical pathway, followed by external irradiation. Radon emanation and consequent doses due to inhalation was not significant. Since the contamination of fresh water aquifers underlying the stacks is of prime concerns, sequential extraction analysis was carried out to define the actual site of 226 Ra and 210 Pb within the solid phosphogypsum material for industries Copebras Ltda, Fosfertil Fertilizantes Fosfatados S.A, Ultrafertil S.A. and Serrana Fertilizantes, named industries A, B, C and D, respectively. The fractions studied in the sequential extraction represent the following chemical phases: water soluble, exchangeable, carbonates, iron oxide, organic and residual. Results obtained for the sequential extraction experiments showed that there are not significant variations in the extraction profiles for 226 Ra and 210 Pb in the various fractions among different types of phosphogypsum samples. Most of these radionuclides was found in the iron oxide fraction (41% to 55%), showing association to Co, Eu, Fe, La, Nd, Sc, Sb and Tb, also available in the same fraction. These elements may be present as a polyphosphate of rare earths and M 2+ elements (M 2+ ) 3 M 3+ (PO 4 ) 3 , which is formed in the presence of phosphoric acid. The cation M 2+ could be Ca 2+ , Ba 2+ , Ra 2+ and Pb 2+ , among other elements present in the formation of phosphogypsum. M 3+ could be La, Nd, Tb, Eu, Sc, Fe or Co. This polyphosphate presents Ra and Pb in its composition and is a double ionised cations scavenger. Amounts ranging from 9% to 18% were uniformly distributed in the first (most labile fraction) and the following two extraction phases (ion exchangeable and carbonate fractions, respectively). The organic and residue fractions formed another group, which presented lower extraction percentages amounts ranging from 2% to 16%. The residual fraction presented the lower extraction percentage, for the two radionuclides studied (2% to 9%) and is associated with higher percentages of Ba, Cr, Hf, Lu, Sb, Sm, Ta, Th, U and Yb. Residues formed in the sequential extraction were analysed by X ray diffractometry, indicating the presence of Si) 2 and BaSO 4 in all residual phases. 226 Ra and 210 Pb present in the residual fraction may be related to barium sulphate or to unreacted phosphatic rock, as silicate or phosphate. Monazite, (M 3+ ,Th)(PO 4 )n, where M 3+ represents 50 to 78% of light rare earths, is one is present in the Brazilian phosphatic rock, is highly insoluble and can explain the presence of Th and rare earths in the residual fraction. (author)

  8. Behavior of Ra-226 and Pb-210 in the aquatical environment of the first Brazilian uranium mine and mill

    Franca, E.P.; Amaval, E.C.S.; Stoffel, M.G.

    1982-01-01

    The first Brazilian uranium mine and mill will start operation in 1981, on the Pocos de Caldas plateau, in the central state of Minas Gerais. The pre-operational environmental survey indicated that the critical radionuclides in the region will be: 226 Ra due to the tailing pond liquid effluent and 21 Pb produced via 222 Rn dispersion, natural fall-out and accumulation on the ground. Sorption and desorption studies of 226 Ra and 210 Pb on their interaction with local water, suspended matter and sediments have been carried out in the laboratory to understand their behavior in the regional aquatic environment. The laboratory experiments gave indications that, in the aquatic environment of Pocos de Caldas, 210 Pb should remain mostly sorbed on bottom sediments. Its transport should occur essentially bound to suspended matter. By contrast, 226 Ra should be transported mostly in the soluble form

  9. Examination of abyssal sea floor and near-bottom water mixing processes using Ra-226 and Rn-222

    Key, R.M.

    1981-01-01

    Since Broecker's (1965) original work, extensive studies have been made on abyssal near-bottom water-mixing processes using the radioactive parent-daughter pair radium-226 (Ra) - radon-222 (Rn). One assumption critical to all of these studies is that sediments immediately under a given water column are the source of excess radon (=Rn concentration - Ra concentration) found in bottom waters. Since 1965 theoretical works of increasing complexity have tried to explain areal variations of excess radon and radium. However, Key et al. (1979b) have reported the only extensive measurements of radium and radon in bottom water and sediments at the same location. This dissertation is an expansion of that work both in theory and in scope. A diagenetic sediment model based on the work of Schink and Guinasso (1978), Cochran (1979), and Key et al. (1979b) was developed to model Ra-Rn in near-surface abyssal sediments. In order to maximize model application information, the degrees of freedom were minimized by measuring as many of the model parameters as possible. The most glaring discrepancy found was that measured near-surface total radium profiles could not be fit using plutonium-derived bioturbation rates. There is an implication that plutonium profiles modeled with currently accepted bioturbation models do not give a true indication of the real biologically induced mixing process. After adjusting for this problem in the source function, diagenetic theory explains near-surface radon-distributions adequately. Using both the adjusted diagenetic model and the empirical model developed by Key et al. (1979b), reasonable agreement was found between the sedimentary radon deficit and near-bottom water surplus. Inadequacy of present diagenetic theory makes any attempt to differentiate sedimentary radium sources academic

  10. Sampling errors associated with soil composites used to estimate mean Ra-226 concentrations at an UMTRA remedial-action site

    Gilbert, R.O.; Baker, K.R.; Nelson, R.A.; Miller, R.H.; Miller, M.L.

    1987-07-01

    The decision whether to take additional remedial action (removal of soil) from regions contaminated by uranium mill tailings involves collecting 20 plugs of soil from each 10-m by 10-m plot in the region and analyzing a 500-g portion of the mixed soil for 226 Ra. A soil sampling study was conducted in the windblown mill-tailings flood plain area at Shiprock, New Mexico, to evaluate whether reducing the number of soil plugs to 9 would have any appreciable impact on remedial-action decisions. The results of the Shiprock study are described and used in this paper to develop a simple model of the standard deviation of 226 Ra measurements on composite samples formed from 21 or fewer plugs. This model is used to predict as a function of the number of soil plugs per composite, the percent accuracy with which the mean 226 Ra concentration in surface soil can be estimated, and the probability of making incorrect remedial action decisions on the basis of statistical tests. 8 refs., 15 figs., 9 tabs

  11. The essential conditions for the choice of location for a long-term storage of radioactive wastes

    Markovic, V.

    1964-10-01

    The paper deals with a long-term storage of radioactive wastes with a special reference to the parameters to be considered in choosing the location. It gives a short account of methods for disposal of radioactive liquid and solid wastes used in nuclear centers in the world. The possibilities of radioactive wastes disposal in our country using the methods investigated are also presented (author)

  12. A review of sorption of radionuclides under the near- and far-field conditions of an underground radioactive waste repository. Pt. 3

    Berry, J.A.

    1992-01-01

    This report summarises work funded by the Department of the Environment and UK Nirex Ltd in the area of sorption of radionuclides under the near-field and far-field conditions pertaining to the underground disposal of radioactive waste in the UK that was presented and discussed in Part I. The report also summarises comparable research undertaken overseas (presented in Part II). (author)

  13. Behaviour at landfills of waste having undergone mechanic-biological and thermal conditioning; Deponieverhalten mechanisch-biologisch und thermisch behandelten Restabfalls

    Danhamer, H.; Dach, J.; Jager, J. [Institut WAR, Darmstadt (Germany). FG Abfalltechnik

    1998-12-31

    The work studies, in landfill test reactors, water, gas and heat transport as well as gas and leachate formation in waste having undergone mechanical-biological and thermal conditioning. (orig.) [Deutsch] Es wurde der Wasser-, Gas- und Waermetransport, sowie die Gasbildung- und Sickerwasserbelastung mechanisch-biologisch und thermisch vorbehandelter Abfaelle in Deponieversuchsreaktoren untersucht. (orig.)

  14. Global warming potential of material fractions occurring in source-separated organic household waste treated by anaerobic digestion or incineration under different framework conditions.

    Naroznova, Irina; Møller, Jacob; Scheutz, Charlotte

    2016-12-01

    This study compared the environmental profiles of anaerobic digestion (AD) and incineration, in relation to global warming potential (GWP), for treating individual material fractions that may occur in source-separated organic household waste (SSOHW). Different framework conditions representative for the European Union member countries were considered. For AD, biogas utilisation with a biogas engine was considered and two potential situations investigated - biogas combustion with (1) combined heat and power production (CHP) and (2) electricity production only. For incineration, four technology options currently available in Europe were covered: (1) an average incinerator with CHP production, (2) an average incinerator with mainly electricity production, (3) an average incinerator with mainly heat production and (4) a state-of-the art incinerator with CHP working at high energy recovery efficiencies. The study was performed using a life cycle assessment in its consequential approach. Furthermore, the role of waste-sorting guidelines (defined by the material fractions allowed for SSOHW) in relation to GWP of treating overall SSOHW with AD was investigated. A case-study of treating 1tonne of SSOHW under framework conditions in Denmark was conducted. Under the given assumptions, vegetable food waste was the only material fraction which was always better for AD compared to incineration. For animal food waste, kitchen tissue, vegetation waste and dirty paper, AD utilisation was better unless it was compared to a highly efficient incinerator. Material fractions such as moulded fibres and dirty cardboard were attractive for AD, albeit only when AD with CHP and incineration with mainly heat production were compared. Animal straw, in contrast, was always better to incinerate. Considering the total amounts of individual material fractions in waste generated within households in Denmark, food waste (both animal and vegetable derived) and kitchen tissue are the main material

  15. Energies and media nr 30. Conditions for the nuclear sector. The fuel cycle and wastes. The usefulness of fuel reprocessing. Wastes

    2009-10-01

    After some comments on recent events in the nuclear sector in different countries (energy policy and projects in the USA, Europe, China, India, Russia), this issue proposes some explanations on the nuclear fuel cycle and on nuclear wastes: involved processes and products from mining to reprocessing and recycling, usefulness of reprocessing (future opportunities of fast neutron reactors, present usefulness of reprocessing with the recycling of separated fissile materials), impact of reprocessing on the environment in La Hague (gas and liquid releases, release standard definition), and the destiny of wastes

  16. Effects of combustion and operating conditions on PCDD/PCDF emissions from power boilers burning salt-laden wood waste.

    Leclerc, Denys; Duo, Wen Li; Vessey, Michelle

    2006-04-01

    This paper discusses the effects of combustion conditions on PCDD/PCDF emissions from pulp and paper power boilers burning salt-laden wood waste. We found no correlation between PCDD/PCDF emissions and carbon monoxide emissions. A good correlation was, however, observed between PCDD/PCDF emissions and the concentration of stack polynuclear aromatic hydrocarbons (PAHs) in the absence of TDF addition. Thus, poor combustion conditions responsible for the formation of products of incomplete combustion (PICs), such as PAHs and PCDD/PCDF precursors, increase PCDD/PCDF emissions. PAH concentrations increased with higher boiler load and/or low oxygen concentrations at the boiler exit, probably because of lower available residence times and insufficient excess air. Our findings are consistent with the current understanding that high ash carbon content generally favours heterogeneous reactions leading to either de novo synthesis of PCDD/PCDFs or their direct formation from precursors. We also found that, in grate-fired boilers, a linear increase in the grate/lower furnace temperature produces an exponential decrease in PCDD/PCDF emissions. Although the extent of this effect appears to be mill-specific, particularly at low temperatures, the results indicate that increasing the combustion temperature may decrease PCDD/PCDF emissions. It must be noted, however, that there are other variables, such as elevated ESP and stack temperatures, a high hog salt content, the presence of large amounts of PICs and a high Cl/S ratio, which contribute to higher PCDD/PCDFs emissions. Therefore, higher combustion temperatures, by themselves, will not necessarily result in low PCDD/PCDFs emissions.

  17. Ha waste conditioning

    Damette, G.

    1986-01-01

    In this report are given a full account of the choice and developments which have led to the continuous vitrification process implemented on industrial scale in the French vitrification facility at MARCOULE (AVM) and in several other installations now at design or construction phase by SGN (Societe Generale des Techniques Nouvelles). Advantages specific to this process are enumerated as well as practical lessons drawn from six years of continuous active operation at MARCOULE. The account concludes with brief description of installations presently being built [fr

  18. Surface and subsurface cleanup protocol for radionuclides Gunnison, Colorado, UMTRA Project Processing Site

    1994-05-01

    The supplemental standards provisions of Title 40, Code of Federal Regulations, Part 192 (40 CFR Part 192) require the cleanup of radionuclides other than radium-226 (Ra-226) to levels ''as low as reasonably achievable'' (ALARA), taking into account site-specific conditions, if sufficient quantities and concentrations are present to constitute a significant radiation hazard. In this context, thorium-230 (Th-230) at the Gunnison, Colorado, processing site will require remediation. However, a seasonally fluctuating groundwater table at the site significantly complicates conventional remedial action with respect to cleanup. Characterization data indicate that in the offpile areas, the removal of residual in situ bulk Ra-226 and Th-230 such that the 1000-year projected Ra-226 concentration (Ra-226 concentration in 1000 years due to the decay of in situ Ra-226 and the in-growth of Ra-226 from in situ Th-230) complies with the US Environmental Protection Agency (EPA) cleanup standard for in situ Ra-226 and the cleanup protocol for in situ Th-230 can be readily achieved using conventional excavation techniques for bulk contamination without encountering significant impacts due to groundwater. The EPA cleanup standard and criterion for Ra-226 and the 1000-year projected Ra-226 are 5 and 15 picocuries per gram (pCi/g) above background, respectively, averaged over 15-centimeter (cm) deep surface and subsurface intervals and 100-square-meter (m 2 ) grid areas. Significant differential migration of Th-230 relative to Ra-226 has occurred over 40 percent of the subpile area. To effectively remediate the site with respect to Ra-226 and Th-230, supplemental standard is proposed and discussed in this report

  19. The experimental testing of the long-term behaviour of cemented radioactive waste from nuclear research reactors in the geological disposal conditions of the boom clay

    Sneyers, A.; Marivoet, J.; Iseghem, P. van

    1998-01-01

    Liquid wastes, resulting from the reprocessing of spent nuclear fuel from the BR-2 Materials Testing Reactor, will be conditioned in a cement matrix at the dedicated cementation facility of UKAEA at Dounreay. In Belgium, the Boom clay formation is studied as a potential host rock for the final geological disposal of cemented research reactor waste. In view of evaluating the safety of disposal, laboratory leach experiments and in situ tests have been performed. Leach experiments in synthetic clay water indicate that the leach rates of calcium and silicium are relatively low compared to those of sodium and potassium. In situ experiments on inactive samples are performed in order to obtain information on the microchemical and mineralogical changes of the cemented waste in contact with the Boom clay. Finally, results from a preliminary performance assessment calculation suggest a non-negligible maximum dose rate of 5 10 -9 Sv/a for 129 I. (author)

  20. Volume reduction and conditioning campaigns, upon low level solid waste drums, realised in ENEA centres of Trisaia (ITREC plant) and Saluggia (EUTREX plant)

    Gili, M.

    1995-09-01

    The volume reduction and conditioning campaigns, upon low level solid waste drums, realized between 1989 and 1993 in the ENEA (Italian Agency for New Technologies, Energy and the Environment) centres of Trisaia (ITREC plant) and Saluggia (EUREX plant), by the mean of supercompactation, and cement immobilization inside over packs, are hereby described. The operational techniques and the equipments used, the whole volume reduction factors obtained and some final considerations over this solid rad wastes treatment procedure are shown. This method, where correctly operated and coupled to an accurate radiological characterization, permits to save space for the waste storage in the short period and to obtain final manufacts, certified suitable for shallow burial disposal, according to italian technical guide n. 26

  1. Royal Order of 30 March 1981 determining the duties and conditions of operation of the public body responsible for radioactive waste and fissile materials management

    1981-01-01

    The purpose of this Royal Order is to set up a public body to be responsible for management of the storage of conditioned radioactive waste, waste disposal, its transport as well as that of plutonium-bearing or enriched fissile materials, and plutonium storage. It must become operational as soon as possible, in particular in the perspective of the Eurochemic Company's technical operations ceasing as from 31 December 1981. This body will be named the National Body for Radioactive Waste and Fissile Materials (ONDRAF). As respects plutonium-bearing or enriched fissile materials, ONDRAF will deal with the transport of materials which, in accordance with the IAEA recommendations [INFCIRC/225/Rev. 1], require physical protection measures (NEA) [fr

  2. The experimental testing of the long-term behaviour of cemented radioactive waste from nuclear research reactors in the geological disposal conditions of the boom clay

    Sneyers, A.; Marivoet, J.; Iseghem, P. van [SCK-CEN, B-2400 Mol (Belgium)

    1998-07-01

    Liquid wastes, resulting from the reprocessing of spent nuclear fuel from the BR-2 Materials Testing Reactor, will be conditioned in a cement matrix at the dedicated cementation facility of UKAEA at Dounreay. In Belgium, the Boom clay formation is studied as a potential host rock for the final geological disposal of cemented research reactor waste. In view of evaluating the safety of disposal, laboratory leach experiments and in situ tests have been performed. Leach experiments in synthetic clay water indicate that the leach rates of calcium and silicium are relatively low compared to those of sodium and potassium. In situ experiments on inactive samples are performed in order to obtain information on the microchemical and mineralogical changes of the cemented waste in contact with the Boom clay. Finally, results from a preliminary performance assessment calculation suggest a non-negligible maximum dose rate of 5 10{sup -9} Sv/a for {sup 129}I. (author)

  3. Evaluation of uranium removal by Hydrilla verticillata (L.f.) Royle from low level nuclear waste under laboratory conditions.

    Srivastava, Sudhakar; Bhainsa, K C

    2016-02-01

    The present study evaluated uranium (U) removal ability and tolerance to low level nuclear waste (LLNW) of an aquatic weed Hydrilla verticillata. Plants were screened for growth in 10%-50% waste treatments up to 3 d. Treatments of 20% and 50% waste imposed increasing toxicity with duration assessed in terms of change in fresh weight and in the levels of photosynthetic pigments and thiobarbituric acid-reactive substances. U concentration, however, did not show a progressive increase and was about 42 μg g(-1) dw from 20% to 50% waste at 3 d. This suggested that a saturation stage was reached with respect to U removal due to increasing toxicity. However, in another experiment with 10% waste and 10% waste+10 ppm U treatments, plants showed an increase in U concentration with the maximum level approaching 426 μg g(-1) dw at 3 d without showing any toxicity as compared to that at 20% and 50% waste treatments. Hence, plants possessed significant potential to take up U and toxicity of LLNW limited their U removal ability. This implies that the use of Hydrilla plants for U removal from LLNW is feasible at low concentrations and would require repeated harvesting at short intervals. Copyright © 2015 Elsevier Ltd. All rights reserved.

  4. Production controls (PC) and technical verification testing (TVT). A methodology for the control and tracking of LILW waste package conditioning

    Leon, A.M.; Nieto, J.L.L.; Garrido, J.G.

    2003-01-01

    As part of its low and intermediate level radioactive waste (LILW) characterisation and acceptance activities, ENRESA has set up a quality control programme that covers the different phases of radioactive waste package production and implies different levels of tracking in generation, assessment of activity and control of the documentation associated therewith. Furthermore, ENRESA has made available the mechanisms required for verification, depending on the results of periodic sampling, of the quality of the end product delivered by the waste producers. Both processes are included within the framework of two programmes of complementary activities: production controls (PC) and technical verification testing (TVT). (orig.)

  5. Assessing and monitoring the effects of filter material amendments on the biophysicochemical properties during composting of solid winery waste under open field and varying climatic conditions.

    Mtimkulu, Y; Meyer, A H; Mulidzi, A R; Shange, P L; Nchu, F

    2017-01-01

    Waste management in winery and distillery industries faces numerous disposal challenges as large volumes of both liquid and solid waste by-products are generated yearly during cellar practices. Composting has been suggested as a feasible option to beneficiate solid organic waste. This incentivized the quest for efficient composting protocols to be put in place. The objective of this study was to experiment with different composting strategies for spent winery solid waste. Compost materials consisting of chopped pruning grape stalks, skins, seed and spent wine filter material consisting of a mixture of organic and inorganic expend ingredients were mixed in compost heaps. The filter material component varied (in percentage) among five treatments: T1 (40%) lined, T2 (20%) lined, T3 (0%) lined, T4 (40%) ground material, lined and T5 (40%) unlined. Composting was allowed to proceed under open field conditions over 12months, from autumn to summer. Indicators such as temperature, moisture, enzyme activities, microbial counts, pH, and C/N ratio, were recorded. Generally, season (df=3, 16, Pwinery solid waste. Copyright © 2016 Elsevier Ltd. All rights reserved.

  6. Struvite recovery from swine waste biogas digester effluent through a stainless steel device under constant pH conditions.

    Perera, P W Anton; Wu, Wei-Xiang; Chen, Ying-Xu; Han, Zhi-Ying

    2009-06-01

    To investigate the struvite precipitation under constant and non-constant pH conditions and to test a stainless steel device under different operating regimes to maximize the recovery of struvite. The molar ratio of NH4+: Mg2+: PO4(3-) was adjusted to 1: 1.2: 1.2 and pH was elevated to 9.0. The absorbance measurement was used to trace the process of struvite crystallization. Wastewater and precipitate analysis was done by standard analytical methods. The pH constant experiment reported a significantly higher struvite precipitation (24.6 +/- 0.86 g) than the non-constant pH experiment (19.8 +/- 1.86 g). The SAR ranged from 5.6 to 8.2 g m(-2) h(-1) to 3.6-4.8 g m(-2) h(-1) in pH constant and non-constant experiments, respectively. The highest struvite deposit on the device was found in regime 3 followed by in regimes 2 and 4. The highest PO4(3-) (97.2%) and NH4+ (71%) removal was reported in the R1 regime. None of the influent Cu2+ or Zn2+ was precipitated on the device. A higher struvite yield is evident in pH constant experiments. Moreover, the stainless steel device facilitates the isolation of heavy metal free pure (around 96%) struvite from swine waste biogas digester effluent contaminated with cu2+ and Zn2+ and the highest yield is attainable with the device operating at 50 rpm with agitation by a magnetic stirrer.

  7. Radioecological condition assessment and remediation criteria for sites of spent fuel and radioactive waste storage in the russian northwest

    Shandala, Nataliya; Titov, Alex; Novikova, Natalia; Kiselev, Mikhail; Romanov, Vladimir; Sneve, Malgorzata; Smith, Graham

    2008-01-01

    The Norwegian Radiation Protection Authority and the Federal Medical-Biological Agency of the Russian Federation have a regulatory cooperation programme which is concerned with management of the nuclear legacy in northwest Russia, and, in particular, the remediation of facilities for spent fuel and radioactive waste management at the former Shore Technical Bases at Andreeva Bay and Gremikha Village. New regulatory guidance documents have been developed, necessary because of the special abnormal situation at these sites, now designated as Sites of Temporary Storage, but also because of the transition from military to civilian regulatory supervision and the evolving regulatory system in the Russian Federation. This paper presents the progress made and on-going projects in 2008 which involve development of the radio-ecological basis for identifying radiation supervision area boundaries and a system of recommended dose constraints and derived control levels for protection of workers and the public. Unconditional guarantee of long-term radioecological protection serves as the basis for criteria development. Non-exceedance of these dose constraints and control levels implies compliance with radiological protection objectives related to the residual contamination. Dose reduction below proposed dose constraint values must also be carried out according to the optimization principle. A number of remediation strategies are considered, corresponding to different future land use assumptions, including interim continued use in a nuclear context. The developed criteria relate to conditions of facilities and surrounding areas at the sites of temporary storage after completion of their remediation, and during the interim stages of remediation, depending upon the remediation strategy adopted. (author)

  8. Waste Incinerator

    1994-05-01

    This book deals with plan and design of waste incinerator, which includes process outline of waste, method of measure, test, analysis, combustion way and classification of incineration facilities, condition of combustion and incineration, combustion calculation and heat calculation, ventilation and flow resistivity, an old body and component materials of supplementary installation, attached device, protection of pollution of incineration ash and waste gas, deodorization, prevention of noise in incineration facility, using heat and electric heat, check order of incineration plan.

  9. Nuclear graphite waste's behaviour under disposal conditions: Study of the release and repartition of organic and inorganic forms of carbon 14 and tritium in alkaline media

    Vende, L.

    2012-01-01

    23000 tons of graphite wastes will be generated during dismantling of the first generation of French reactors (9 gas cooled reactors). These wastes are classified as Long Lived Low Level wastes (LLW-LL). As requested by the law, the French National Radioactive Waste Management Agency (Andra) is studying concepts of low-depth disposals.In this work we focus on carbon 14, the main long-lived radionuclide in graphite waste (5730 y), but also on tritium, which is the main contributor to the radioactivity in the short term. Carbon 14 and tritium may be released from graphite waste in many forms in gaseous phase ( 14 CO 2 , HT...) or in solution ( 14 CO 3 2- , HTO...). Their speciation will strongly affect their migration from the disposal site to the environment. Leaching experiments, in alkaline solution (0.1 M NaOH simulating repository conditions) have been performed on irradiated graphite, from Saint-Laurent A2 and G2 reactors, in order to quantify their release and characterize their speciation. The studies show that carbon 14 exists in both gaseous and aqueous phases. In the gaseous phase, release is weak (≤0.1%) and corresponds to oxidizable species. Carbon 14 is mainly released into liquid phase, as both inorganic and organic species. 65% of released fraction is inorganic and 35% organic carbon. Two tritiated species have been identified in gaseous phase: HTO and HT/Organically Bond Tritium. More than 90% of tritium in that phase corresponds to HT/OBT. But release is weak (≤0.1%). HTO is mainly in the liquid phase. (author)

  10. Some aspects of the technology improvement for heat reprocessing of the combustible radioactive wastes and ash residue conditioning

    Dmitriev, S.A.; Lifanov, F.A.; Knyazev, I.A.; Buravchenko, N.N.; Sobolev, I.A.; Mamaev, L.A.; Alekseev, A.N.; Simagina, O.S.

    1991-01-01

    The results of studies devoted to increasing the efficiency of thermal reprocessing (combustion) of organic low- and intermediate-level radioactive wastes are given. The new most efficient three-stage process including: 1) gasification and pyrolysis of an organic material with volatile product release, 2) coke residual combustion, ash and noncombustible materials melting, 3) combustion of volatile products of thermal decomposition is developed on the basis of the analysis of solid radioactive waste combustion schemes, mathematical simulation and laboratory studies. Experimental bed, in which these processes are realized, is created. The results obtained in it have allowed one to begin designing of the pilot-commercial plant with shaft furnace having the capacity up to 200 kg/h for solid wastes

  11. Implications of synergetic indirect effects and increased flexibility for municipal solid waste management within future framework conditions

    Cimpan, Ciprian; Rothmann, Marianne; Wenzel, Henrik

    and compared against a large variety of background system scenarios, consisting of the most probable future development of the Danish energy system (and surrounding countries) towards 2050. Specific focus was placed on identification and modelling of possible indirect effects on adjoining systems that would......Life cycle assessments addressing municipal solid waste management systems (MSWMS) most often represent and evaluate these systems or compare isolated technological and management solutions in a much too simplistic interaction with their surroundings, accounting for a minimum of probable future...... potential (GWP) of different waste management strategies. Within the study reported here, a number of alternative MSWMS were simulated and evaluated, comprising combinations of separate collection and different downstream treatment/handling approaches for remaining residual waste, including advanced...

  12. Containers and overpacks for high-level radioactive waste in deep geological disposal. Conditions: French Corrosion Programme

    Crusset, D.; Plas, F.; Santarini, G.

    2003-01-01

    Within the framework of the act of French law dated 31 December, 1991, ANDRA (National Radioactive Waste Management Agency) is responsible for conducting the feasibility study on disposal of reversible and irreversible high-level or long-life radioactive waste in deep geological formations. Consequently, ANDRA is carrying out research on corrosion of the metallic materials envisaged for the possible construction of overpacks for vitrified waste packages or containers for spent nuclear fuel. Low-alloy or unalloyed steels and the passive alloys (Fe-Ni-Cr-Mo) constitute the two families of materials studied and ANDRA has set up a research programme in partnership with other research organisations. The 'broad outlines' of the programme, which includes experimental and modelling operations, are presented. (authors)

  13. Spent fuel and high level waste: Chemical durability and performance under simulated repository conditions. Results of a coordinated research project 1998-2004. Part 2: Results of a previously unpublished CRP: Performance of high level waste forms and packages under repository conditions. Results of a co-ordinated research project 1991-1998

    2007-07-01

    The objective of the CRP (Coordinated Research Projekt) on the 'Performance of High Level Waste Forms and Packages under Repository Conditions' was to contribute to the development and implementation of proper and sound technologies for HLW and spent fuel management. Special emphasis was given to the identification of various waste form properties and the study of their long term durability in simulated repository conditions. Another objective was to promote the co-operation and exchange of information between Member States on experimental concerning behaviour of the waste form. The CRP was composed of research contracts and agreements with Argentina, Australia, Belgium, Canada, China, Czech Republic, Finland, France, Germany, India, Japan, Russia, and the United States of America. The publication includes 14 individual contributions of the participants to the CRP, which are indexed separately.

  14. Management of radioactive waste

    Neerdael, B.; Marivoet, J.; Put, M.; Van Iseghem, P.; Volckaert, G.; Wacquier, W.

    1998-09-01

    The document gives an overview of of different aspects of radioactive waste management in Belgium. The document discusses the radioactive waste inventory in Belgium, the treatment and conditioning of radioactive waste as well as activities related to the characterisation of different waste forms. A separate chapter is dedicated to research and development regarding deep geological disposal of radioactive waste. In the Belgian waste management programme, particular emphasis is on studies for disposal in clay. Main results of these studies are highlighted and discussed

  15. Assessment of site conditions for disposal of low- and intermediate-level radioactive wastes: A case study in southern China

    Yi, Shuping; Ma, Haiyi; Zheng, Chunmiao; Zhu, Xiaobin; Wang, Hua'an; Li, Xueshan; Hu, Xueling; Qin, Jianbo

    2012-01-01

    Near surface disposal of low- and intermediate-level radioactive wastes (LILW) requires evaluating the field conditions of the candidate site. However, assessment of the site conditions may be challenging due to the limited prior knowledge of some remote sites, and various multi-disciplinary data requirements at any given site. These situations arise in China as in the rest of the industrialized world, particularly since a regional strategy for LILW disposal has been implemented to protect humans and the environment. This paper presents a demonstration of the site assessment process through a case study focusing mainly on the geologic, hydrogeologic and geochemical characteristics of the candidate site. A joint on-site and laboratory investigation, supplemented by numerical modeling, was implemented in this assessment. Results indicate that no fault is present in the site area, although there are some minor joints and fractures, primarily showing a north–south trend. Most of the joints are filled with quartz deposits and would thus function hydraulically as impervious barriers. Investigation of local hydrologic boundaries has shown that the candidate site represents an essentially isolated hydrogeologic unit, and that little or no groundwater flow occurs across its boundaries on the north or east, or across the hilly areas to the south. Groundwater in the site area is recharged by precipitation and discharges primarily by evapo-transpiration and surface flow through a narrow outlet to the west. Groundwater flows slowly from the hilly area to the foot of the hills and discharges mainly into the inner brooks and marshes. Some groundwater circulates in deeper granite in a slower manner. The vadose zone in the site was investigated specially for their significant capability for restraining the transport of radionuclides. Results indicate that the vadose zone is up to 38 m in thickness and is made up of alluvial clay soils and very highly weathered granite. The vadose

  16. Existing conditions socioeconomic portion. Waste isolation pilot plant environmental impact report, chapter 2, sections 2. 2, 2. 3

    1978-07-01

    The population characteristics and the economic setting of Eddy and Lea Counties, New Mexico, are reviewed as related to site selection for a radioactive waste isolation pilot plant. Sections are included on population distribution, basic industries, trade and services, financial resources, personal income, tourism, labor force, employment, land use, water systems, utilities, transportation, and local government. (JRD)

  17. Existing conditions socioeconomic portion. Waste isolation pilot plant environmental impact report, chapter 2, sections 2.2, 2.3

    1978-07-01

    The population characteristics and the economic setting of Eddy and Lea Counties, New Mexico, are reviewed as related to site selection for a radioactive waste isolation pilot plant. Sections are included on population distribution, basic industries, trade and services, financial resources, personal income, tourism, labor force, employment, land use, water systems, utilities, transportation, and local government

  18. The long-term behaviour of cemented research reactor waste under the geological disposal conditions of the Boom Clay Formation: results from leach experiments

    Sneyers, A.; Fays, J.; Iseghem, P. van

    2001-01-01

    The Belgian Nuclear Research Centre SCK-CEN has carried out a number of studies to evaluate the long-term behaviour of cemented research reactor waste under the geological disposal conditions of the Boom Clay Formation. Static leach experiments in synthetic clay water were performed on active samples of cemented research reactor waste. The leach experiments were carried out under anaerobic conditions at two testing temperatures (23 and 85 o C). Leach rates of seven radionuclides ( 60 Co, 90 Sr, 134 Cs, 137 Cs, 144 Ce, 154 Eu and 241 Am) were measured. Most investigated radionuclides are well retained within the cement matrix over a 280 days testing period. Results on the source term of radionuclides were complemented with data on the leaching behaviour of cement matrix constituents as Ca, Si, Al, Na, K, Mg and SO 4 as well as with data from performance assessment calculations and in situ tests. Despite limitations inherent to short-term experiments, combined results from these investigations indicate only limited interactions of disposed research reactor waste with the near field of a geological repository in clay. (author)

  19. Final deposition of high-level nuclear waste in very deep boreholes. An evaluation based on recent research of bedrock conditions at great depths

    Aahaell, Karl-Inge

    2007-01-01

    This report evaluates the feasibility of very deep borehole disposal of high-level nuclear waste, e.g., spent nuclear fuel, in the light of recent technological developments and research on the characteristics of bedrock at extreme depths. The evaluation finds that new knowledge in the field of hydrogeology and technical advances in drilling technology have advanced the possibility of using very deep boreholes (3-5 km) for disposal of the Swedish nuclear waste. Decisive factors are (1) that the repository can be located in stable bedrock at a level where the groundwater is isolated from the biosphere, and (2) that the waste can be deposited and the boreholes permanently sealed without causing long-term disturbances in the density-stratification of the groundwater that surrounds the repository. Very deep borehole disposal might offer important advantage compared to the relatively more shallow KBS approach that is presently planned to be used by the Swedish nuclear industry in Sweden, in that it has the potential of being more robust. The reason for this is that very deep borehole disposal appears to permit emplacement of the waste at depths where the entire repository zone would be surrounded by stable, density-stratified groundwater having no contact with the surface, whereas a KBS-3 repository would be surrounded by upwardly mobile groundwater. This hydro-geological difference is a major safety factor, which is particularly apparent in all scenarios that envisage leakage of radioactive substances. Another advantage of a repository at a depth of 3 to 5 km is that it is less vulnerable to impacts from expected events (e.g., changes in groundwater conditions during future ice ages) as well as undesired events (e.g. such as terrorist actions, technical malfunction and major local earthquakes). Decisive for the feasibility of a repository based on the very deep borehole concept is, however, the ability to emplace the waste without failures. In order to achieve this

  20. Assessment of site conditions for disposal of low- and intermediate-level radioactive wastes: a case study in southern China.

    Yi, Shuping; Ma, Haiyi; Zheng, Chunmiao; Zhu, Xiaobin; Wang, Hua'an; Li, Xueshan; Hu, Xueling; Qin, Jianbo

    2012-01-01

    Near surface disposal of low- and intermediate-level radioactive wastes (LILW) requires evaluating the field conditions of the candidate site. However, assessment of the site conditions may be challenging due to the limited prior knowledge of some remote sites, and various multi-disciplinary data requirements at any given site. These situations arise in China as in the rest of the industrialized world, particularly since a regional strategy for LILW disposal has been implemented to protect humans and the environment. This paper presents a demonstration of the site assessment process through a case study focusing mainly on the geologic, hydrogeologic and geochemical characteristics of the candidate site. A joint on-site and laboratory investigation, supplemented by numerical modeling, was implemented in this assessment. Results indicate that no fault is present in the site area, although there are some minor joints and fractures, primarily showing a north-south trend. Most of the joints are filled with quartz deposits and would thus function hydraulically as impervious barriers. Investigation of local hydrologic boundaries has shown that the candidate site represents an essentially isolated hydrogeologic unit, and that little or no groundwater flow occurs across its boundaries on the north or east, or across the hilly areas to the south. Groundwater in the site area is recharged by precipitation and discharges primarily by evapo-transpiration and surface flow through a narrow outlet to the west. Groundwater flows slowly from the hilly area to the foot of the hills and discharges mainly into the inner brooks and marshes. Some groundwater circulates in deeper granite in a slower manner. The vadose zone in the site was investigated specially for their significant capability for restraining the transport of radionuclides. Results indicate that the vadose zone is up to 38m in thickness and is made up of alluvial clay soils and very highly weathered granite. The vadose