Durability studies on the high calcium flyash based GPC

African Journals Online (AJOL)

Keywords: Geopolymer concrete, high calcium flyash, durability, corrosion resistance, polarisation test. ... Reddy, et al (2011) reported that excellent resistance to chloride .... being the metal on the higher electro potential range, to the negative ...

Problems and prospects of refuse disposal in nigerian urban centres ...

African Journals Online (AJOL)

Refuse disposal is one of the major environmental problems that developing ... The problem of waste management has two parts, that of collection and that of disposal. ... Disposal methods such as dumping sites, incineration, recycling, shipping ... citizenry has roles to play in adopting more suitable solutions to this problem.

Effect of Fly-Ash on Corrosion Resistance Characteristics of Rebar Embedded in Recycled Aggregate Concrete

Science.gov (United States)

Revathi, Purushothaman; Nikesh, P.

2018-04-01

In the frame of an extended research programme dealing with the utilization of recycled aggregate in concrete, the corrosion resistance characteristics of rebars embedded in recycled aggregate concrete is studied. Totally five series of concrete mixtures were prepared with fly-ash as replacement for cement in the levels of 10-30% by weight of cement. Corrosion studies by 90 days ponding test, linear polarization test and impressed voltage tests were carried out, in order to investigate whether corrosion behaviour of the rebars has improved due to the replacement of cement with fly-ash. Results showed that the replacement of cement with fly-ash in the range of 20-30% improves the corrosion resistance characteristics of recycled aggregate concrete.

Preparation of poly-o-phenylenediamine/TiO2/fly-ash cenospheres and its photo-degradation property on antibiotics

International Nuclear Information System (INIS)

Huo Pengwei; Yan Yongsheng; Li Songtian; Li Huaming; Huang Weihong

2010-01-01

A series of poly-o-phenylenediamine/TiO 2 /fly-ash cenospheres(POPD/TiO 2 /fly-ash cenospheres) composites have been prepared from o-phenylenediamine and TiO 2 /fly-ash cenospheres under various polymerization conditions. The properties of the samples were characterized by scanning electron microscopy (SEM), energy dispersive spectroscopy (EDS), specific surface area (BET), X-ray diffraction (XRD), Fourier transform infrared (FT-IR) and UV-vis diffuse reflectance spectrum (UV-vis DRS). Photocatalytic activity was studied by degradation of antibiotics waste water under visible light. The results indicate that the photo-induced method is viable for preparing modified photocatalysts, and the modified photocatalysts have good absorption in visible light range. The photocatalysts of POPD/TiO 2 /fly-ash cenospheres which have good performance are prepared at pH 3 and 4, and the polymerized time around 40 min. When the photocatalysts are prepared under the conditions of pH 3 and polymerized time 40 min, the degradation rate of roxithromycin waste water could reach near 60%, and it indicates that the way of POPD modified TiO 2 /fly-ash cenospheres to degrade the antibiotics waste water is viable.

Application of spherical fly-ash particles to study spatial deposition of atmospheric pollutants in northen-eastern Estonia

International Nuclear Information System (INIS)

Alliksaar, T.

2000-01-01

Spherical fly-ash particles, emitted to the atmosphere in the high-temperature combustion process of fossil fuels, were found in considerable amounts in analysed snow samples of north-eastern Estonia. Spatial deposition of particles in snow cover is compared with the results of surface sediment samples of lakes. The results from snow characterise well the distribution of pollution sources and the distance from the main power plants in north eastern Estonia. Variations in particle deposition of closely situated snow samples were found to be negligible. Fly-ash particle influxes in snow samples correlate well with modelled maximum concentration fields of flyash in the near-surface air layer. (author)

Selective preparation of zeolite X and A from flyash and its use as catalyst for biodiesel production

Energy Technology Data Exchange (ETDEWEB)

Volli, Vikranth; Purkait, M.K., E-mail: mihir@iitg.ernet.in

2015-10-30

Highlights: • Flyash was utilized for zeolites preparation for transesterification. • Single phase and highly crystalline zeolite was obtained at flyash/NaOH ratio of 1:1.2. • Si/Al ratio of 2 resulted in the formation of zeolite X. • At 5 wt% of catalyst loading conversion was 84.6%. • The biodiesel obtained has a calorific value of 37.5 MJ/Kg. - Abstract: This work discusses the utilization of flyash for synthesis of heterogeneous catalyst for transesterification. Different types of zeolites were synthesized from alkali fusion followed by hydrothermal treatment of coal flyash as source material. The synthesis conditions were optimized to obtain highly crystalline zeolite based on degree of crystallinity and cation exchange capacity (CEC). The effect of CEC, acid treatment, Si/Al ratio and calcination temperature (800, 900 and 1000 °C) on zeolite formation was also studied. Pure, single phase and highly crystalline zeolite was obtained at flyash/NaOH ratio (1:1.2), fusion temperature (550 °C), fusion time (1 h), hydrothermal temperature (110 °C) and hydrothermal time (12 h). The synthesized zeolite was ion-exchanged with potassium and was used as catalyst for transesterification of mustard oil to obtain a maximum conversion of 84.6% with 5 wt% catalyst concentration, 12:1 methanol to oil molar ratio, reaction time of 7 h at 65 °C. The catalyst was reused for 3 times with marginal reduction in activity.

Influence of vermiculite on performance of flyash-based fibre-reinforced hybrid composites as friction materials

International Nuclear Information System (INIS)

Satapathy, Bhabani K.; Patnaik, Amar; Dadkar, Nandan; Kolluri, Dilip K.; Tomar, Bharat S.

2011-01-01

Highlights: → Study successfully demonstrates the possibility of designing fibre reinforced friction materials with vermiculite-flyash combination. → Vermiculite has caused an increase in the post-braking onset of degradation temperature. → Fade behaviour was found to be optimally dependent on the flyash-vermiculite combination whereas recovery remained broadly unaffected. → Vermiculite caused reduction in the maximum disc temperature rise and enhanced the frictional amplitude, i.e. μ max -μ min . → Static-friction, fade and recovery acted as major determinants for the overall friction performance whereas wear remained thermally activated. -- Abstract: Flyash-based fibre-reinforced hybrid phenolic composites filled with vermiculite were fabricated and characterized for their physical, thermal, mechanical and tribological performance. The performance were evaluated in terms of their friction-fade, friction-recovery, maximum disc temperature rise and wear behaviour on a Krauss friction tester conforming to the Regulation-90 as per the Economic Commission for Europe (ECE) norms. The fade behaviour has been observed to be optimally dependent on the flyash-vermiculite combination whereas the recovery remained broadly unaffected at ∼112 ± 14%. Addition of vermiculite has contributed to the reduction in the maximum disc temperature rise whereas it enhanced the frictional amplitude, i.e. μ max -μ min . The wear behaviour remains closely related to the trend observed in fade. The addition of vermiculite has caused an increase in the post-braking onset of degradation temperature of the surface composition as compared to the pre-braking composition. The analyses of friction and wear performance of the composites were carried out and major factors influencing the tribo-performance were identified. Worn surface morphology investigation using scanning electron microscope has revealed that the addition of vermiculite alters the compositional interactions at the

Conduction mechanism in Polyaniline-flyash composite material for shielding against electromagnetic radiation in X-band & Ku band

Directory of Open Access Journals (Sweden)

Avanish Pratap Singh

2011-06-01

Full Text Available β–Naphthalene sulphonic acid (β–NSA doped polyaniline (PANI–flyash (FA composites have been prepared by chemical oxidative polymerization route whose conductivity lies in the range 2.37–21.49 S/cm. The temperature dependence of electrical conductivity has also been recorded which shows that composites follow Mott's 3D–VRH model. SEM images demonstrate that β–NSA leads to the formation of the tubular structure with incorporated flyash phase. TGA studies show the improvement in thermal stability of composites with increase in loading level of flyash. Complex parameters i.e. permittivity (ɛ* = ɛ′- iɛ″ and permeability (μ*=μ′- iμ″ of PANI-FA composites have been calculated from experimental scattering parameters (S11 & S21 using theoretical calculations given in Nicholson–Ross and Weir algorithms. The microwave absorption properties of the composites have been studied in X-band (8.2 – 12.4 GHz & Ku–Band (12.4 – 18 GHz frequency range. The maximum shielding effectiveness observed was 32dB, which strongly depends on dielectric loss and volume fraction of flyash in PANI matrix.

Development of marine flyash concrete and evaluation of its performance with respect to physico-chemical and biological factors in marine environment

Digital Repository Service at National Institute of Oceanography (India)

Jayakumar, S.; VijayKumar, V.; Kundaikar, T.J.; Venugopal, C.; Sawant, S.S.

The aim of the research was to develop flyash concrete and assess various factors controlling its durability in the marine environment. Hence the research was planned with the following objectives in mind: (1) Development of flyash concrete...

Effect of composition variations on the long-term wasteform behavior of vitrified domestic waste incineration fly-ash purification residues

International Nuclear Information System (INIS)

Frugier, Pierre

1999-01-01

The effect of variations in the composition of fly-ash purification residue from incinerated domestic waste on the quality of the containment achieved by vitrification was investigated. Three main factors determine the long-term containment quality: the production of a vitrified wasteform, the occurrence of possible crystallization, and the key parameters of long-term alteration in aqueous media. Each of these aspects is described within a composition range defined by variations in the three major elements. (silicon, calcium and aluminum) and two groups of constituents (alkali metals and toxic elements). The silicon fraction in the fly-ash residue was found to be decisive: it is impossible to obtain a satisfactory vitrified wasteform below a given silicon concentration. Compounds with the lowest silica content also exhibited the greatest tendency to crystallize under the cooling conditions prevailing in industrial processes (the dominant crystallized phase is a melilite that occupies a significant fraction of the material and considerably modifies the alteration mechanisms). The initial alteration rate in pure water and the altered glass thickness measured in a closed system at an advanced stage of the dissolution reaction are both inversely related to the silicon concentration in the glass. Several types of long-term behavior were identified according to the composition range, the process conditions and the vitrified waste disposal scenario. Four distinct 'classes' of vitrified wasteform were defined for direct application in industrial processes. (author) [fr

Experimental Research on Foamed Mixture Lightweight Soil Mixed with Fly-Ash and Quicklime as Backfill Material behind Abutments of Expressway Bridge

Directory of Open Access Journals (Sweden)

Xin Liu

2017-01-01

Full Text Available To promote the utilization of fly-ash, based on the orthogonal experiment method, wet density and unconfined compressive strength of Foamed Mixture Lightweight Soil mixed with fly-ash and quicklime (FMLSF are studied. It is shown that the wet density and unconfined compressive strength of FMLSF increase with the increase of cement content, while decreasing with the increase of foam content. With the mixing content of fly-ash increase, the wet density and unconfined compressive strength of FMLSF increase firstly and then decrease. Scanning Electron Microscope (SEM tests show that ball effect or microaggregate effect of fly-ash improves the wet density and unconfined compressive strength of FMLSF. With the mixing content of quicklime increase, the wet density and unconfined compressive strength of FMLSF increase firstly within a narrow range and then decrease. In addition, the primary and secondary influence order on wet density and 28-day compressive strength of FMLSF are obtained, as well as the optimal mixture combination. Finally, based on two abutments in China, behind which they are filled with FMLSF and Foamed Mixture Lightweight Soil (FMLS, the construction techniques and key points of quality control behind abutment are compared and discussed in detail, and the feasibility of utilization fly-ash as FMLSF is verified by the experimental results.

Chemical and Nuclear Waste Disposal: Problems and Solutions

OpenAIRE

James P. Murray; Joseph J. Harrington; Richard Wilson

1982-01-01

The problems of waste disposal have always been with us. In biblical times, the residents of Jerusalem always burnt their wastes inthehideousValeofGehenna.Thisgavewaytoburialofwasteor sometimes dumping it in shallow oceans. All too often the sewage pipes of the seaside towns did not even take the waste to the low tide mark; and the use of the deep oceans as a disposal site has been almost unknown...

Spent fuel disposal problem in Bulgaria

Energy Technology Data Exchange (ETDEWEB)

Milanov, M; Stefanova, I [Bylgarska Akademiya na Naukite, Sofia (Bulgaria). Inst. za Yadrena Izsledvaniya i Yadrena Energetika

1994-12-31

The internationally agreed basic safety principles and criteria for spent fuel (SF) and high level waste (HLW) disposal are outlined. In the framework of these principles the specific problems of Bulgaria described in the `National Concept for Radioactive Waste Management and Disposal in Republic of Bulgaria` are discussed. The possible alternatives for spent fuel management are: (1) sending the spent fuel for disposal in other country; (2) once-through cycle and (3) closed fuel cycle. A mixed solution of the problem is implemented in Bulgaria. According to the agreement between Bulgaria and former Soviet Union a part of the spent fuel has been returned to Russia. The once-through and closed-fuel cycle are also considered. The projected cumulated amount of spent fuel is estimated for two cases: (1) the six units of Kozloduy NPP are in operation till the end of their lifetime (3300 tHM) and (2) low estimate (2700 tHM) - only units 5 and 6 are operated till the end of their lifetime. The reprocessing of the total amount of 3300 tHM will lead to the production of about 370 m{sup 3} vitrified high level wastes. Together with the HLW about 1850 m{sup 3} cladding hulls and 7800 m{sup 3} intermediate-level wastes will be generated, which should be disposed off in deep geological repository. The total production of radioactive waste in once-through cycle is 181 000 m{sup 3}, and in closed cycle - 190 000 m{sup 3}. Geological investigations are performed resulting in categorization of the territory of the country based on geological, geotechnical and hydrogeological conditions. This will facilitate the choice of the most suitable location for deep geological repository. 7 figs., 11 refs.

Disposal of low-level radioactive waste using high-calcium fly ash. Final report

International Nuclear Information System (INIS)

Cogburn, C.O.; Hodgson, L.M.; Ragland, R.C.

1986-04-01

The feasibility of using calcium-rich fly ash from coal-fired power plants in the disposal of low-level radioactive waste was examined. The proposed areas of use were: (1) fly-ash cement as a trench lining material; (2) fly ash as a backfill material; and (3) fly ash as a liquid waste solidifier. The physical properties of fly-ash cement were determined to be adequate for trench liner construction, with compressive strengths attaining greater than 3000 psi. Hydraulic conductivities were determined to be less than that for clay mineral deposits, and were on the order of 10 -7 cm/sec, with some observed values as low as 10 -9 cm/sec. Removal of radioisotopes from acidified solutions by fly ash was good for all elements tested except cesium. The removal of cesium by fly ash was similar to that of montmorillonite clay. The corrosive effects on metals in fly ash environments was determined to be slight, if not non-existent. Coatings at the fly-ash/metal interfaces were observed which appeared to inhibit or diminish corrosion. The study has indicated that high-calcium fly ash appears to offer considerable potential for improved retention of low-level radioactive wastes in shallow land disposal sites. Further tests are needed to determine optimum methods of use. 8 refs., 4 figs., 7 tabs

Numerical convergence for a sewage disposal problem

OpenAIRE

Alvarez-Vázquez, L.J.; Martínez, A.; Rodríguez, C.; Vázquez-Méndez, M.E.

2001-01-01

The management of sewage disposal and the design of wastewater treatment systems can be formulated as a constrained pointwise optimal control problem. In this paper we study the convergence of the numerical resolution for the corresponding state system by means of a characteristics Galerkin method. The main difficulty of the problem is due to the existence of Radon measures in the right-hand side of the state system. Finally, we present numerical results for a realistic problem posed in a ria...

Adsorption of radioactive I2 gas onto fly-ash aerosol

International Nuclear Information System (INIS)

Noguchi, Hiroshi; Murata, Mikio; Suzuki, Katsumi.

1988-01-01

The adsorption of radioactive elemental iodine (I 2 ) gas onto fly-ash aerosol has been studied to provide basic data for the realistic and precise assessment of dose to the general public from radioiodine released from nuclear facilities. A mixture of fly-ash aerosol and 131 I 2 gas was passed through a cylindrical glass vessel so that particulate iodine was formed by adsorption of I 2 onto aerosol. Then the concentrations of I 2 and particulate iodine were measured. It was found that the adsorption reached an equilibrium state between 5 and 12 min and that the proportion of iodine which was adsorbed on the aerosol decreased with increasing initial I 2 concentration ranging over 10 -13 to 10 -9 g/cm 3 . The adsorption isotherm of the aerosol for I 2 gas approximately followed Freundlich isotherm. Using the adsorption isotherm, a theoretical equation was derived to explain the adsorption on the basis of FUCHS' theory on the evaporation of droplets. A sticking probability in the equation decreased with increasing adsorbed amount. The calculated results were in good agreement with the experimental ones. (author)

The use of fly-ash particles for dating lake sediments

Energy Technology Data Exchange (ETDEWEB)

Rose, N L [Environmental Change Research Centre, University College London, London (United Kingdom)

1998-08-01

Fly-ash particles comprise two particle types, spheroidal carbonaceous particles (SCP) and inorganic ash spheres (IAS). In lake sediments, these particles form an unambiguous record of atmospheric deposition of industrial pollutants. The main temporal trends of these sediment records have been found to be remarkably consistent over wide geographical areas and these features can be used to ascribe dates to cores undated by other means. SCP are the main particle type used in this way as they are easier to extract and enumerate. IAS are morphologically similar to some natural particles (volcanic, meteoritic) and therefore show a natural background concentration at all pre-industrial sediment depths. Apart from this background temporal trends are similar to SCP and IAS could be used for dating in the same way. Gaining an indication of fuel-type change, either from IAS:SCP ratio or chemical characterization of SCP enables additional dates to be added to sediment cores through comparison with documentary evidence. In the future, as {sup 210}Pb becomes progressively unable to date the post-industrial sediment record, dating using fly-ash techniques may become increasingly important. (orig.) 17 refs.

The use of fly-ash particles for dating lake sediments

International Nuclear Information System (INIS)

Rose, N.L.

1998-01-01

Fly-ash particles comprise two particle types, spheroidal carbonaceous particles (SCP) and inorganic ash spheres (IAS). In lake sediments, these particles form an unambiguous record of atmospheric deposition of industrial pollutants. The main temporal trends of these sediment records have been found to be remarkably consistent over wide geographical areas and these features can be used to ascribe dates to cores undated by other means. SCP are the main particle type used in this way as they are easier to extract and enumerate. IAS are morphologically similar to some natural particles (volcanic, meteoritic) and therefore show a natural background concentration at all pre-industrial sediment depths. Apart from this background temporal trends are similar to SCP and IAS could be used for dating in the same way. Gaining an indication of fuel-type change, either from IAS:SCP ratio or chemical characterization of SCP enables additional dates to be added to sediment cores through comparison with documentary evidence. In the future, as 210 Pb becomes progressively unable to date the post-industrial sediment record, dating using fly-ash techniques may become increasingly important. (orig.)

Experimental study of fly-ash migration by using magnetic method

Czech Academy of Sciences Publication Activity Database

Kapička, Aleš; Kodešová, R.; Petrovský, Eduard; Hůlka, Z.; Grison, Hana; Kaška, M.

2011-01-01

Roč. 55, č. 4 (2011), s. 683-696 ISSN 0039-3169 R&D Projects: GA AV ČR IAA300120701 Grant - others:GA AV ČR(CZ) M100120901 Institutional research plan: CEZ:AV0Z30120515 Keywords : environmental magnetism * fly-ash migration * magnetic susceptibility * SM400 Kappameter Subject RIV: DK - Soil Contamination ; De-contamination incl. Pesticides Impact factor: 0.700, year: 2011

Selective preparation of zeolite X and A from flyash and its use as catalyst for biodiesel production.

Science.gov (United States)

Volli, Vikranth; Purkait, M K

2015-10-30

This work discusses the utilization of flyash for synthesis of heterogeneous catalyst for transesterification. Different types of zeolites were synthesized from alkali fusion followed by hydrothermal treatment of coal flyash as source material. The synthesis conditions were optimized to obtain highly crystalline zeolite based on degree of crystallinity and cation exchange capacity (CEC). The effect of CEC, acid treatment, Si/Al ratio and calcination temperature (800, 900 and 1000 °C) on zeolite formation was also studied. Pure, single phase and highly crystalline zeolite was obtained at flyash/NaOH ratio (1:1.2), fusion temperature (550 °C), fusion time (1 h), hydrothermal temperature (110 °C) and hydrothermal time (12h). The synthesized zeolite was ion-exchanged with potassium and was used as catalyst for transesterification of mustard oil to obtain a maximum conversion of 84.6% with 5 wt% catalyst concentration, 12:1 methanol to oil molar ratio, reaction time of 7 h at 65 °C. The catalyst was reused for 3 times with marginal reduction in activity. Copyright © 2015 Elsevier B.V. All rights reserved.

Laboratory evaluation of flyash treated embankment and base materials : interim report No. 1.

Science.gov (United States)

1986-06-01

This study was undertaken to provide the Louisiana DOTD with a data base from which decision-making information can be concerning the modification or stabilization of soils using flyash as a full or partial replacement for hydraulic cement or hydrate...

Main approaches to solving the problems of radioactive waste processing and disposal

International Nuclear Information System (INIS)

Tarasov, V.M.; Syrkus, M.N.

1989-01-01

papers devoted to the problems of processing and disposal of radioactive wastes, formed during nuclear facility operation and after decommissioning are reviewed. Techniques for gaseous and liquid waste solidification, as well as solid waste processing by mechanical fragmentation and combustion are considered. Possibilities of radioactive waste disposal in cosmic space, their burial at the bed of seas ansd oceans, in geological storages are discussed. Special attention disposal. The conclusion is made that today there are no any uniform way for radiactive waste disposal and standard technical means for its realization. Solution of the problems considered should be of a complex character and it is carried out within international research programs

Geological aspects of the nuclear waste disposal problem

International Nuclear Information System (INIS)

Laverov, N.P.; Omelianenko, B.L.; Velichkin, V.I.

1994-06-01

For the successful solution of the high-level waste (HLW) problem in Russia one must take into account such factors as the existence of the great volume of accumulated HLW, the large size and variety of geological conditions in the country, and the difficult economic conditions. The most efficient method of HLW disposal consists in the maximum use of protective capacities of the geological environment and in using inexpensive natural minerals for engineered barrier construction. In this paper, the principal trends of geological investigation directed toward the solution of HLW disposal are considered. One urgent practical aim is the selection of sites in deep wells in regions where the HLW is now held in temporary storage. The aim of long-term investigations into HLW disposal is to evaluate geological prerequisites for regional HLW repositories

Radioactive waste disposal in deep geologic deposits. Associated research problems

International Nuclear Information System (INIS)

Rousset, G.

1992-01-01

This paper describes the research associated problems for radioactive waste disposal in deep geologic deposits such granites, clays or salt deposits. After a brief description of the underground disposal, the author studies the rheology of sedimentary media and proposes rheological models applied to radioactive wastes repositories. Waste-rock interactions, particularly thermal effects and temperature distribution versus time. 17 refs., 14 figs

Effects of Vinegar Bad and Flyash on the Growth of Sorghum and the Improvement of Saline Soils

Directory of Open Access Journals (Sweden)

FAN Na

2017-10-01

Full Text Available Based on the sorghum growth and salinity soil improvement, the effects of vinegar bad and flyash on the growth of sorghum and the improvement of saline soils were studied. The experiment was carried out with random block design, in 4 treatment, which were pure vinegar bad(treatment 1, vinegar bad and fly ash 1:1 ratio(treatment 2, vinegar bad and fly ash 2:1 ratio(treatment 3 and control respectively. The results showed that the contents of available nutrient in the four periods of sorghum growth increased firstly and then decreased, and the effect of vinegar bad and flyash treatment was better than that of control. Among them, the ratio 1:1 of vinegar and fly ash had the best effect. The results showed that compared with the control, the soil bulk density of treatment 1~3 was decreased by 19.6%, 28.6% and 11.32%, respectively. The spike length of treatment 1~3 was 6.25%, 9.06%, 3.93% higher than that of the control, respectively. The yield per plant of treatment 1~3 was increased by 10.53%, 13.26% and 8.89%, respectively. In summary, vinegar bad, flyash could improve the physical and chemical properties of saline soil, improve the environment of deep soil for plant growth, thereby increase the yield of sorghum.

Buildup of gamma ray photons in flyash concretes: A study

International Nuclear Information System (INIS)

Singh, Sukhpal; Ghumman, S.S.; Singh, Charanjeet; Thind, Kulwant Singh; Mudahar, Gurmel S.

2010-01-01

The gamma ray buildup factors of flyash concretes have been calculated by using Geometrical Progression formula in the energy region of 0.015-15 MeV as well as up to a penetration depth of 40 mean free paths, and have been studied as a function of incident photon energy. From the obtained results it is seen that for a fixed penetration depth the values of buildup factor are very large in the medium energy region and are small in the low and high energy regions. The results have been shown graphically.

Experience of NS disposal at the Enterprise ''Zvezdochka'', in Severodvinsk. Problems of ecological safety

International Nuclear Information System (INIS)

Kozlov, Yuri

1999-01-01

According to this presentation, decommissioning and disposal of nuclear submarines is a problem of great concern in Russia. So far more than 150 nuclear submarines have been removed from the Fleet and will be disposed of. Future disposals were not taken into consideration when the shipyards were constructed. Nuclear vessels with loaded cores stay afloat waiting for their turn to be disposed of, often with damaged safety assurance systems and a potential for causing major ecological catastrophes. The presentation deals briefly with some international programmes in progress at Nerpa in Murmansk, Zvezda in Primorye and Zvezdochka in Arkhangelsk and then discusses in more detail the experience of disposal at the Zvezdochka, which under the Start-2 agreement is defined as one of the enterprises dealing with the disposal of strategic nuclear submarines. There they have the qualified staff and the equipment needed. Spent nuclear fuel unloading and removal is the most acute problem

Development of modified flyash as a permeable reactive barrier medium for a former manufactured gas plant site, Northern Ireland

Science.gov (United States)

Doherty, R.; Phillips, D. H.; McGeough, K. L.; Walsh, K. P.; Kalin, R. M.

2006-05-01

A sequential biological permeable reactive barrier (PRB) was determined to be the best option for remediating groundwater that has become contaminated with a wide range of organic contaminants (i.e., benzene, toluene, ethylbenzene, xylene and polyaromatic hydrocarbons), heavy metals (i.e., lead and arsenic), and cyanide at a former manufactured gas plant after 150 years of operation in Portadown, Northern Ireland. The objective of this study was to develop a modified flyash that could be used in the initial cell within a sequential biological PRB to filter complex contaminated groundwater containing ammonium. Flyash modified with lime (CaOH) and alum was subjected to a series of batch tests which investigated the modified cation exchange capacity (CEC) and rate of removal of anions and cations from the solution. These tests showed that a high flyash composition medium (80%) could remove 8.65 mol of ammonium contaminant for every kilogram of medium. The modified CEC procedure ruled out the possibility of cation exchange as the major removal mechanism. The medium could also adsorb anions as well as cations (i.e., Pb and Cr), but not with the same capacity. The initial mechanism for Pb and Cr removal is probably precipitation. This is followed by sorption, which is possibly the only mechanism for the removal of dichromate anions. Scanning electron microscopic analysis revealed very small (productive zeolite formation. Surface area measurements showed that biofilm growth on the medium could be a major factor in the comparative reduction of surface area between real and synthetic contaminant groundwaters. The modified flyash was found to be a highly sorptive granular material that did not inhibit microbiological activity, however, leaching tests revealed that the medium would fail as a long-term barrier material.

Phytoextraction crop disposal--an unsolved problem

International Nuclear Information System (INIS)

Sas-Nowosielska, A.; Kucharski, R.; Malkowski, E.; Pogrzeba, M.; Kuperberg, J.M.; Krynski, K.

2004-01-01

Several methods of contaminated crop disposal after phytoextraction process (composting, compaction, incineration, ashing, pyrolysis, direct disposal, liquid extraction) have been described. Advantages and disadvantages of methods are presented and discussed. Composting, compaction and pyrolysis are the pretreatment steps, since significant amount of contaminated biomass will still exist after each of the process. Four methods of final disposal were distinguished: incineration, direct disposal, ashing and liquid extraction. Among them, incineration (smelting) is proposed as the most feasible, economically acceptable and environmentally sound. - Methods of contaminated crop disposal are described and evaluated

Problems and approach to geological disposal of radioactive waste

International Nuclear Information System (INIS)

Kitayama, Kazumi; Yamazaki, Haruo; Ijiri, Yuji; Haga, Kazuko; Sakamaki, Masanori; Kishi, Kiyoshi

2006-01-01

This feature articles described a concept and technical problems of geological disposal of high-level radioactive waste in the civil engineering. It consists of six papers such as the present statues and subjects of geological disposal by KITAYAMA Kazumi, the diastrophism, igneous activity, and upheaval and erosion by YAMAZAKI Haruo, the groundwater flow and evaluation of nuclear transfer by IJIRI Yuji, evaluation of alteration of cement materials in the ultra-long period by HAGA Kazuko, The Mizunami Underground Research Laboratory in course of construction by SAKAMAKI Masanori, and interview of the ninetieth president of JSCE (Japan Society of Civil Engineers), he places his hope on JSCE and civil engineers by KISHI Kiyoshi. (S.Y.)

Novel porous fly-ash containing geopolymer monoliths for lead adsorption from wastewaters

Energy Technology Data Exchange (ETDEWEB)

Novais, Rui M., E-mail: ruimnovais@ua.pt; Buruberri, L.H.; Seabra, M.P.; Labrincha, J.A.

2016-11-15

Highlights: • Porous fly ash containing-geopolymer monoliths for lead adsorption were developed. • Geopolymers’ porosity and pH of the ion solution controls the adsorption capacity. • Lead adsorption by the geopolymer monoliths up to 6.34 mg/g was observed. • These novel adsorbents can be used in packed beds that are easily collected. • The reuse of biomass fly ash wastes as raw material ensures waste valorization. - Abstract: In this study novel porous biomass fly ash-containing geopolymer monoliths were produced using a simple and flexible procedure. Geopolymers exhibiting distinct total porosities (ranging from 41.0 to 78.4%) and low apparent density (between 1.21 and 0.44 g/cm{sup 3}) were fabricated. Afterwards, the possibility of using these innovative materials as lead adsorbents under distinct conditions was evaluated. Results demonstrate that the geopolymers’ porosity and the pH of the ion solution strongly affect the lead adsorption capacity. Lead adsorption by the geopolymer monoliths ranged between 0.95 and 6.34 mg{sub lead}/g{sub geopolymer}. More porous geopolymers presented better lead removal efficiency, while higher pH in the solution reduced their removal ability, since metal precipitation is enhanced. These novel geopolymeric monoliths can be used in packed beds that are easily collected when exhausted, which is a major advantage in comparison with the use of powdered adsorbents. Furthermore, their production encompasses the reuse of biomass fly-ash, mitigating the environmental impact associated with this waste disposal, while decreasing the adsorbents production costs.

Environmental issues of disposal of wastes from thermal power plants

International Nuclear Information System (INIS)

Ghosh, R.; Sinha, T.K.; Saxena, N.C.

1998-01-01

Experiments were undertaken to find out means to use the fly ash ponds as useful fertile land which will result in an environment friendly fly ash disposal system. The results showed: (i) fly-ash mixed with 50% or even 25% soil can support on it vegetables like tomato, brinjal, kholrabi, chilly and ladies finger, food crops like wheat, bazra and paddy and pulses like arhar, (ii) fly ash ponds without any amendment can support growth of lemon-grass, (iii) another set of experiments have shown that normal leaching of fly ash by rain water or tap water does not draw any pollutant from it, (iv) long term leaching through months can draw negligible amounts of Cu, Zn, Mn, Fe, etc. which may not result in any effective ground water pollution. (author)

Regulatory, administrative and financial problems raised by radioactive waste disposal

International Nuclear Information System (INIS)

Reyners, P.

1980-03-01

This paper analyses the salient aspects of the non-technical problems involved in radioactive waste disposal: the division of operational, regulatory and administrative responsibilities, the usefulness of providing a form of institutional control of the waste disposed of, and the question of the length of time for such mechanisms, both of which are closely linked to the preceding point. A description follows of the R and D financing mechanisms in the field and of the surveillance systems to be set up. Finally, mention is made of the legal and practical difficulties encountered in the application of the third party liability and insurance regime to long-term waste management and the international dimension of all these questions. (NEA) [fr

Operation of a low-level waste disposal facility and how to prevent problems in future facilities

International Nuclear Information System (INIS)

Di Sibio, R.

1985-01-01

Operation of a low-level waste facility is an ever increasing problem nationally, and specifically one that could grow to crisis proportion in Pennsylvania. There have been, nevertheless, a variety of changes over the years in the management of low level radioactive waste, particularly with regard to disposal facilities that can avert a crisis condition. A number of companies have been organized thru possible a broad range of services to the nuclear industry, including those that emphasize solidification of waste materials, engineering services, waste management, and transportation to disposal sites across the United States. This paper addresses one particular site and the problems which evolved at that site from an environmental perspective. It is important that it is clearly understood that, although these problems are resolvable, the lessons learned here are critical for the prevention of problems at future facilities. The focus of this paper is on the Maxey Flats, Kentucky disposal facility which was closed in 1977. It must be understood that the regulations for siting, management, burial techniques, waste classification, and the overall management of disposal sites were limited when this facility was in operation

Uranium mill tailings storage, use, and disposal problems

International Nuclear Information System (INIS)

Hendricks, D.W.

1977-01-01

Solid and liquid residues (tailings) containing substantial quantities of naturally occurring radionuclides are produced and stored at all US uranium mill sites. These radioactive wastes are a potential health hazard with the degree of hazard depending largely on the tailings management practices at the individual sites. The principal pathways of potential radiation exposure to man are discussed. A description is presented of some past and current tailings storage practices together with a description of some of the possible problems associated with various stabilization and disposal options. 16 figures

Wood waste: A disposal problem or an opportunity?

International Nuclear Information System (INIS)

Vajda, P.

1989-01-01

The utilization of wood wastes in North America is reviewed, with a focus on the wood products industry and markets. On the whole, wood mill residues in North America have always been utilized except for a period from the 1940s to the 1970s oil crisis. In the latter period, low cost electric power and hydrocarbon fuels rendered uneconomical the use of wood wastes as fuel. As a response to the problem of disposing these wastes, a number of innovations occurred in that period, including the use of wood chips for manufacturing pulp and particleboard, and the use of sawdust and shavings for manufacturing hardboard and medium density fiberboard. Uses for bark, except as fuel, have not been successfully developed. Since the 1970s, wood waste in the USA is essentially all used for composite board products and fuel. This is also true in eastern Canada, which is close to the wood products markets and which has fairly high oil and gas costs. However, in western Canada, low energy costs and small internal markets have led to a serious wood waste disposal problem. A survey of wood waste supply and demand shows large surpluses in mill residues in western Canada and some remote locations in northern Ontario and Quebec. The Pacific Rim countries are identified as a potential market for western Canadian composite board production. The use of other sources of wood waste (forestry or logging residues, which are costly to collect, and municipal construction waste) is briefly discussed

Some geotechnical problems related to underground waste disposal in salt formations

International Nuclear Information System (INIS)

Berest, P.

1993-01-01

Nuclear waste disposal in deep salt formations is an option considered by several countries. Rock salt is a very impervious medium, but can be easily leached; selection of an appropriate disposal formation must account for natural protections of the formation as regards water movements. It must be checked that such initially favourable characteristics will not be affected by the existence of shafts and galleries, or by the important heat output generated by vitrified wastes. The discussion is uneasy, for a comprehensive rheological model for rock salt is difficult to set and to be extrapolated to large time scales; some methodological problems are raised by use of numerical computations. (author). 22 refs., 2 figs

Numerical simulation of fly-ash transport in three sands of different particle-size distributions using HYDRUS-1D

Czech Academy of Sciences Publication Activity Database

Kodešová, R.; Kapička, Aleš; Lebeda, J.; Grison, Hana; Kočárek, M.; Petrovský, Eduard

2011-01-01

Roč. 59, č. 3 (2011), s. 206-216 ISSN 0042-790X R&D Projects: GA AV ČR IAA300120701 Institutional research plan: CEZ:AV0Z30120515 Keywords : sand * fly-ash migration * magnetic susceptibility * numerical simulation * attachment /detachment concept * filtration theory Subject RIV: DK - Soil Contamination ; De-contamination incl. Pesticides Impact factor: 0.340, year: 2011

Fundamental problem of high-level radioactive waste disposal policy in Japan. Critical analysis responding to the publication of 'Nationwide Map of Scientific Features for Geological Disposal' by the Japanese government

International Nuclear Information System (INIS)

Juraku, Kohta

2017-01-01

The government explains that 'Scientific Characteristic Map' (hereinafter 'Map') shows the scientific characteristics of sites that are thought necessary to be taken into account when choosing the place to implement geological disposal and their geographical distribution on the Japanese map for the convenience to 'roughly overlook.' Nuclear Waste Management Organization of Japan (NUMO) as the implementing agency for geological disposal and the government (Agency for Natural Resources and Energy of Ministry of Economy, Trade and Industry) stress that this Map does not indicate so-called 'optimum land,' but it is the 'first step of a long way to realize disposal' for high-level radioactive waste (HLW). However, there clearly lurks a debate about the acceptance of the location of geological disposal in the future. The author has pointed out that the essence of the HLW disposal problem is a problem of 'value selection' that should be decided prior to the location of disposal site. The author believes that it is the competence of society how to identify the path of countermeasures by reconciling in a high degree the justice of the policies supported by scientific and professional knowledge and the justice of social decision making through a democratic duty process. However, the government is trying to forward HLW disposal only from the viewpoint of location problems, while neglecting the problem of 'value selection.' (A.O.)

Fly-ash poisoning in the surroundings of foundries

Energy Technology Data Exchange (ETDEWEB)

Hupka, E

1955-01-01

Chronic articular swellings were observed in colts and cattle grazing in the vicinity of two factories. Postmortem findings included an increased synovial content and a detachment of articular cartilage from the underlying bone. Several of the colts also developed roaring due to paralysis of the recurrent nerves. Analysis of fly-ash samples from the two foundries revealed the following: lead, 16.87 percent and 44.79 percent; zinc, 23.41 percent and 5.28 percent; sulfur, 12.53 percent and 8.20 percent; and arsenic, 0.52 percent and 0.22 percent, respectively. Cadmium levels of 2.22 percent were also found in the dust from one of foundries, while cerium (5.00 percent) was detected in the dust from the other foundry. Identical articular lesions were reproduced in two colts receiving dietary rations containing the forge dusts. Manifestations of pharyngoparalysis also appeared, resulting in pneumonia in one case due to pharyngeal dysphagia. Lead poisoning, complicated by other toxic substances, was suggested as the cause. Analyses of several colt livers revealed contents exceeding 0.2 mg/100 g in all cases.

Corrosion problems related to the containment of high-level nuclear waste for disposal

Energy Technology Data Exchange (ETDEWEB)

Rothwell, G P

1981-10-01

The subject is examined under the headings: introduction (nature of problem; system of barriers which will initially contain the wasteform and subsequently limit the rate of transport of products from the wasteform to the external environment); environmental data (disposal in land-based repositories; disposal on or in the deep seabed); design philosophies and materials data (design; criteria for materials selection (kinetics of corrosion)); specific materials considerations (environmental parameters -temperature, pressure, heat transfer and radiation effects; single metals and alloys - steels, nickel based alloys, copper, lead, titanium, aluminium oxide); alternative approaches; an overview - information needs; summary.

Encouraging Sustainable Transport Choices in American Households: Results from an Empirically Grounded Agent-Based Model

Directory of Open Access Journals (Sweden)

�ubica Kozáková

2013-12-01

Full Text Available This study was concerned with solidification/stabilisation (S/S process of municipal solid waste incineration (MSWI fly-ashes produced in the plant located in Ko�ice (Slovakia by cementation with a special interest in binding leachable heavy metals. Waste incineration is a commonly used technique for waste processing and disposal connected to production of MSWI fly-ash. Fly-ash is classified as hazardous waste due to high heavy metals content, and very fine particles. Two types of MSWI fly-ashes, collected from the cyclones (assigned as C and from the filters (assigned as F of the flue gas cleaning plant, were studied. By the S/S process using Portland cement both the fly-ashes were stabilised and the highest fly-ash:cement ratio to prepare firm stabilised samples were found to be 1:1.45 and 6:1 for the fly-ashes F and C, respectively. These differences were caused by different composition of the fly-ashes that significantly influence the S/S process, especially low chlorides content, and presence of sulphates and quartzin the fly-ash C and highchlorides and sulphides and low quartz content, absence of sulphates, and higher contents of lead and zinc in the fly-ash F. Special interest was paid on Ni, Cr, Cd, Cu, Zn, and Pb leaching from both the non-stabilised and the stabilised MSWI fly-ashes. Ni showed the highest and Zn the lowest leaching ratios for both the non-stabilised MSWI fly-ashes. All the monitored heavy metals leached from both the stabilised MSWI fly-ashes in concentrations below 0.03 mg.l-1. The leachates of both the solidified MSWI fly-ashes showed a significant immobilisation of the heavy metals in the stabilised product with a decrease of the leaching ability by more than 99 %. The stabilised MSWI fly-ashes can bedeposited in landfills for inert waste.

Nuclear waste disposal. A wicked and highly conflict bearing societal problem

International Nuclear Information System (INIS)

Brunnengraeber, Achim; Mez, Lutz

2012-01-01

The final disposal of nuclear wastes is called ''messy'' or ''wicked'' in the political science literature. The highly complicated problems are characterized by a number of features such as intra- and inter-generational aspects and ethical questions. In the case of stakeholders the differences concern ideologies, interests, merits and preferences that cause conflicts. The search for solutions is complicated due to interacting political, social, ecologic, economic and technical aspects. The concepts ''wicked problems'' and ''multi-level-governance'' are promising approaches to solve the complicated situation.

Corrosion problems related to the containment of high-level nuclear waste for disposal

International Nuclear Information System (INIS)

Rothwell, G.P.

1981-01-01

The subject is examined under the headings: introduction (nature of problem; system of barriers which will initially contain the wasteform and subsequently limit the rate of transport of products from the wasteform to the external environment); environmental data (disposal in land-based repositories; disposal on or in the deep seabed); design philosophies and materials data (design; criteria for materials selection (kinetics of corrosion)); specific materials considerations (environmental parameters -temperature, pressure, heat transfer and radiation effects; single metals and alloys - steels, nickel based alloys, copper, lead, titanium, aluminium oxide); alternative approaches; an overview - information needs; summary. (U.K.)

Disposal - practical problems

International Nuclear Information System (INIS)

Hycnar, J.; Pinko, L.

1995-01-01

Most Polish power plants have stockyards for storage of fly ash and slag. This paper describes the: methods of fly ash and slag storage used, methods of conveying the waste to the stockpiles (by railway cars, trucks, belt conveyors or hydraulically); construction of wet stockyards and dry stockyards and comparison of the ash dumped, development of methods of ash disposal in mine workings; composition and properties of fly ash and slag from hard coal; and the effects of ash storage yards on the environment (by leaching of trace elements, dust, effect on soils, and noise of machinery). 16 refs., 3 figs., 6 tabs

Rock disposal problems identified

Energy Technology Data Exchange (ETDEWEB)

Knox, R

1978-06-01

Mathematical models are the only way of examining the return of radioactivity from nuclear waste to the environment over long periods of time. Work in Britain has helped identify areas where more basic data is required, but initial results look very promising for final disposal of high level waste in hard rock repositories. A report by the National Radiological Protection Board of a recent study, is examined.

Legal and administrative problems related to the treatment and disposal of radioactive wastes

International Nuclear Information System (INIS)

Cornelis, J.C.

1976-01-01

The consequence of the rapid expansion of nuclear power programmes is that the quantity of radioactive wastes will increase in proportion. These wastes are produced during the different stages of the fuel cycle. The management of these wastes raises certain legal problems particularly regarding the methods for final storage or for sea disposal. All these management methods have an international incidence and these aspects must be studied in step with technical problems. (N.E.A.) [fr

Twenty-three years of vegetation change in a fly-ash leachate impacted meadow

Science.gov (United States)

Pavlovic, Noel B.; Leicht-Young, Stacey A.; Wilcox, Douglas; Hiebert, Ron; Murphy, Marilyn K.; Mason, Daniel; Frohnapple, Krystal

2009-01-01

1. Blag Slough, located in Indiana Dunes National Lakeshore, has received leachates from nearby fly-ash ponds for 13 years (1967-1980). We have monitored vegetation and sediment of Blag Slough since 1982, two years after the sealing of the fly-ash ponds and one year after the substrate was first exposed. The pH of the soil has increased one order of magnitude from 3.0 to 4.0 over the 23 years (1982-2005). If the pH further increases the solubility of many heavy metals will decrease, except for arsenic. We provide evidence that boron and zinc were bioaccumulating in the leaves of woody plants in 1984. The ratio of leaf concentration and soil concentration of aluminum suggests this element was not bioaccumulating in woody plants in 1984. 2. Soil concentrations of iron, aluminum, arsenic, and strontium were higher nearest the fly-ash ponds in 2005. The southwest corner of Blag Slough and middle position of transect X had the highest elevated levels of these metals and correlated with the occurrence of mixed spikerush association (dominated by Eleocharis olivacea). 3. Only a few exotic species occurred in the Blag Slough. Common reed (Phragmites australis) was among such species that occurred in three large clones. Other exotic species included dandelion (Taraxacum officinale), mullein (Verbascum thapsis), Jerusalem oak goosefoot (Chenopodium botrys), and sheep sorrel (Rumex acetosella). Ruderal species have occurred including thistle (Cirsium spp.), fire weed (Erechtites hieracifolium), and horseweed (Conyza canadensis). While occasional cattail (Typha) have been sampled and mapped in Blag Slough they have never persisted for very long. 4. Species richness leveled off between 1991 and 2005, except for Transect X that had a peak in 1986-7. After an extreme rainfall event in August 18, 1990, Transect V had an average water depth of 0.70 cm, W had 7.1 cm, and X had 26.90 cm. Richness in Transect X declined to a low level in 1990 and 1991 after the extreme flooding event

Diffusion of He in OPC paste and low-heat Portland cement paste containing fly-ash in contact with aqueous phase

International Nuclear Information System (INIS)

Sato, Fuminori; Miwata, Chikanori; Noda, Natsuko; Sato, Seichi; Kozaki, Tamotsu; Higashihara, Tomohiro; Hironaga, Michihiko; Kawanishi, Motoi

2008-01-01

As a part of gas migration studies in concrete package for nuclear waste surrounded by water-saturated rock, the helium diffusion in ordinary Portland cement paste (OPC) was studied using disk form specimen at various water-to-cement (w/c) ratios. The helium diffusion in low-heat Portland cement paste containing fly-ash (LPF) was also studied. Apparent diffusion coefficients of helium in OPC paste were ∼1 x 10 -10 m 2 s -1 at 0.4 w/c ratio, independent of increase of w/c ratio. It is likely that the materials formation such as C-S-H and CH in capillary pores in OPC plays an important role on the helium diffusion rather than porosity increase. Apparent diffusion coefficient of helium in LPF was two orders of magnitude smaller than that in OPC. It is quite possible that the addition of fly-ash contributes to the formation of hydration products which markedly enhance discontinuity of capillary pore. The results of the present study on the two kinds of cement pastes give us valuable information about alternatives to release gas from cement package. (author)

Waste disposal: preliminary studies

International Nuclear Information System (INIS)

Carvalho, J.F. de.

1983-01-01

The problem of high level radioactive waste disposal is analyzed, suggesting an alternative for the final waste disposal from irradiated fuel elements. A methodology for determining the temperature field around an underground disposal facility is presented. (E.G.) [pt

Electromagnetic problems in nuclear waste disposal

International Nuclear Information System (INIS)

Eloranta, E.H.

1998-01-01

The paper reviews the electromagnetic characterization of fractured rock during various phases of radioactive waste disposal investigations and construction, and also discusses the methods of the electromagnetic safeguards monitoring

Cosmic disposal of radioactive waste

Energy Technology Data Exchange (ETDEWEB)

Inoue, Y; Morisawa, S [Kyoto Univ. (Japan). Faculty of Engineering

1975-03-01

The technical and economical possibility and safety of the disposal of highly radioactive waste into cosmos are reviewed. The disposal of highly radioactive waste is serious problem to be solved in the near future, because it is produced in large amounts by the reprocessing of spent fuel. The promising methods proposed are (i) underground disposal, (ii) ocean disposal, (iii) cosmic disposal and (iv) extinguishing disposal. The final disposal method is not yet decided internationally. The radioactive waste contains very long life nuclides, for example transuranic elements and actinide elements. The author thinks the most perfect and safe disposal method for these very long life nuclides is the disposal into cosmos. The space vehicle carrying radioactive waste will be launched safely into outer space with recent space technology. The selection of orbit for vehicles (earth satellite or orbit around planets) or escape from solar system, selection of launching rocket type pretreatment of waste, launching weight, and the cost of cosmic disposal were investigated roughly and quantitatively. Safety problem of cosmic disposal should be examined from the reliable safety study data in the future.

Effect of composition variations on the long-term wasteform behavior of vitrified domestic waste incineration fly-ash purification residues; Influence des variations de composition des vitrifiats de refiom - residus d'epuration des fumees d'incineration d'ordures menageres - sur leur comportement a long terme

Energy Technology Data Exchange (ETDEWEB)

Frugier, P.

2000-07-01

The effect of variations in the composition of fly-ash purification residue from incinerated domestic waste on the quality of the containment achieved by vitrification was investigated. Three main factors determine the long-term containment quality: the production of a vitrified wasteform, the occurrence of possible crystallization, and the key parameters of long-term alteration in aqueous media. Each of these aspects is described within a composition range defined by variations in the three major elements. (silicon, calcium and aluminum) and two groups of constituents (alkali metals and toxic elements). The silicon fraction in the fly-ash residue was found to be decisive: it is impossible to obtain a satisfactory vitrified wasteform below a given silicon concentration. Compounds with the lowest silica content also exhibited the greatest tendency to crystallize under the cooling conditions prevailing in industrial processes (the dominant crystallized phase is a melilite that occupies a significant fraction of the material and considerably modifies the alteration mechanisms). The initial alteration rate in pure water and the altered glass thickness measured in a closed system at an advanced stage of the dissolution reaction are both inversely related to the silicon concentration in the glass. Several types of long-term behavior were identified according to the composition range, the process conditions and the vitrified waste disposal scenario. Four distinct 'classes' of vitrified wasteform were defined for direct application in industrial processes. (author)

Degradation of toxic contaminants in water using nanotitania on flyash substrate

Science.gov (United States)

Sharma, Richa; Madan, Shubhangi; Tiwari, Sangeeta

2018-05-01

Photocatalysis has been of significant interest due to its new technology for environmental pollution. Titanium dioxide is known to be extensively used photocatalyst for the removal of environmental contaminants. In the present work, the generation of TiO2 nanoparticles by the thermal decomposition of titanium tetraisopropoxide (TTIP) on flyash core was carried out by insitu precipitation technique. Photodegradation of methylene blue as a water pollutant was carried out experimentally using self-made laboratory photocatalytic reactor and then photocatalytic properties of prepared core shell composite are studied by using UV light. Absorbance spectra were measured at different time interval using a spectrophotometer and the concentration of the test solution was calculated. Effect of different annealing temperatures on dye degradation was studied. Composite particles annealed at 800°C showed almost 82% of removal of the dye in just 10 minutes. Our test results showed that prepared composite material is a promising material for treating wastewater.

Solving a multi-objective location routing problem for infectious waste disposal using hybrid goal programming and hybrid genetic algorithm

Directory of Open Access Journals (Sweden)

Narong Wichapa

2018-01-01

Full Text Available Infectious waste disposal remains one of the most serious problems in the medical, social and environmental domains of almost every country. Selection of new suitable locations and finding the optimal set of transport routes for a fleet of vehicles to transport infectious waste material, location routing problem for infectious waste disposal, is one of the major problems in hazardous waste management. Determining locations for infectious waste disposal is a difficult and complex process, because it requires combining both intangible and tangible factors. Additionally, it depends on several criteria and various regulations. This facility location problem for infectious waste disposal is complicated, and it cannot be addressed using any stand-alone technique. Based on a case study, 107 hospitals and 6 candidate municipalities in Upper-Northeastern Thailand, we considered criteria such as infrastructure, geology and social & environmental criteria, evaluating global priority weights using the fuzzy analytical hierarchy process (Fuzzy AHP. After that, a new multi-objective facility location problem model which hybridizes fuzzy AHP and goal programming (GP, namely the HGP model, was tested. Finally, the vehicle routing problem (VRP for a case study was formulated, and it was tested using a hybrid genetic algorithm (HGA which hybridizes the push forward insertion heuristic (PFIH, genetic algorithm (GA and three local searches including 2-opt, insertion-move and interexchange-move. The results show that both the HGP and HGA can lead to select new suitable locations and to find the optimal set of transport routes for vehicles delivering infectious waste material. The novelty of the proposed methodologies, HGP, is the simultaneous combination of relevant factors that are difficult to interpret and cost factors in order to determine new suitable locations, and HGA can be applied to determine the transport routes which provide a minimum number of vehicles

Problems and prospects for nuclear waste disposal policy

International Nuclear Information System (INIS)

Herzik, E.B.; Mushkatel, A.H.

1996-01-01

This book is a collection of articles examining legal, organizational, and public-interest issues involving the transportation, storage, treatment, and disposal of radioactive wastes. The introductions examines the unresolved issues of nuclear-waste policy-making in the USA and then presents essays covering the disposal of commercial power plant fuel, low level radioactive wastes, the by-products of nuclear weapons production, and the challenges of transporting radiological materials

Disposing of coal combustion residues in inactive surface mines: Effects on water quality

International Nuclear Information System (INIS)

Kim, A.G.; Ackman, T.E.

1994-01-01

The disposal of coal combustion residues (CCR) in surface and underground coal mines can provide a stable, low-maintenance alternative to landfills, benefiting the mining and electric power industries. The material may be able to improve water quality at acid generating abandoned or reclaimed coal mine sites. Most combustion residues are alkaline, and their addition to the subsurface environment could raise the pH, limiting the propagation of pyrite oxidizing bacteria and reducing the rate of acid generation. Many of these CCR are also pozzolanic, capable of forming cementitious grouts. Grouts injected into the buried spoil may decrease its permeability and porosity, diverting water away from the pyritic material. Both mechanisms, alkaline addition and water diversion, are capable of reducing the amount of acid produced at the disposal site. The US Bureau of Mines is cooperating in a test of subsurface injection of CCR into a reclaimed surface mine. Initially, a mixture of fly ash, lime, and acid mine drainage (AMD) sludge was injected. Lime was the source of calcium for the formation of the pozzolanic grout. Changes in water quality parameters (pH, acidity, anions, and trace metals) in water samples from wells and seeps indicate a small but significant improvement after CCR injection. Changes in the concentration of heavy metals in the water flowing across the site were apparently influenced by the presence of flyash

Dynamics of deposited fly-ash and fine grained magnetite in sandy material of different porosity (column experiments)

Science.gov (United States)

Kapicka, Ales; Kodesova, Radka; Petrovsky, Eduard; Grison, Hana

2010-05-01

Several studies confirm that soil magnetometry can serve as proxy of industrial immisions as well as heavy-metal contamination. The important assumption for magnetic mapping of contaminated soils is that atmospherically deposited particulate matter, including the ferrimagnetic phase, accumulates in the top soil horizons and remains there over long period. Only if this is true, large areas can be reliably mapped using soil magnetometry, and, moreover, this method can be used also for long-term monitoring. However, in soil types such as sandy soils with different porosity or soils with substantial variability of water regime, translocation of the deposited anthropogenic particles may result in biased (underestimated) values of the measured topsoil magnetic susceptibility. From the physical point of view, this process may be considered as colloid transport through porous medium. In our column experiments in laboratory we used three technical sands with different particle sizes (0,63 - 1.25mm, 0,315-0,80mm, 0,10-0,63mm). Sands in cylinders were contaminated on the surface by fly-ashes from coal-burning power plant (mean grain size 10μm) and fine grained Fe3O4 (grain size < 20 μm). Soil moisture sensors were used to monitor water regime within the sand columns after controlled rain simulation and temperature distribution in sand column was measured as well. Vertical migration of ferrimagnetic particles-tracers presented in the fly-ash was measured by SM 400 Kappameter. By means of magnetic susceptibility distribution we studied two parameters: gradual shift of peak concentration of contaminants (relative to surface layer) and maximum penetration depth. Results indicated that after rain simulation (pulls infiltration of defined water volume) the positions of peak values moved downwards compared to the initial state and gradual decrease of susceptibility peak values were detected in all studied sand formations. Fly-ash migrated more or less freely in coarse sand

Separation and chemical characterization of finely-sized fly-ash particles

International Nuclear Information System (INIS)

Campbell, J.A.; Laul, J.C.; Nielson, K.K.; Smith, R.D.

1978-01-01

The concentrations of 43 major, minor, and trace elements were measured by x-ray fluorescence, atomic absorption, and instrumental neutron activation for nine well-defined size fractions, with mass median diameters of 0.5 μ to 50 μm, of fly ash from a western coal-fired steam plant. There was generally good agreement in concentrations of elements analyzed by more than one technique. Concentration profiles as a function of mean particle size were established for various elements. Based on the concentration profiles, the elements can be divided into three distinct groups. One group consists primarily of the volatile elements or elements partially volatilized during coal combustion (examples include As, Se, Zn, Ga, etc.), and their concentrations decrease with increasing particle size. A second group, which shows a minor or direct dependence on particle size, as in the case of Si, is apparently associated primarily with the fly-ash matrix. The last group of elements, which includes Ca, Sr, Y, and the rare earths, shows small changes in their concentration profiles with a maximum in concentration at approximately 5 μm. 6 tables, 6 figures

Influence of relative trophic position and carbon source on selenium bioaccumulation in turtles from a coal fly-ash spill site

International Nuclear Information System (INIS)

Van Dyke, James U.; Hopkins, William A.; Jackson, Brian P.

2013-01-01

Selenium (Se) is a bioaccumulative constituent of coal fly-ash that can disrupt reproduction of oviparous wildlife. In food webs, the greatest enrichment of Se occurs at the lowest trophic levels, making it readily bioavailable to higher consumers. However, subsequent enrichment at higher trophic levels is less pronounced, leading to mixed tendencies for Se to biomagnify. We used stable isotopes ( 15 N and 13 C) in claws to infer relative trophic positions and relative carbon sources, respectively, of seven turtle species near the site of a recently-remediated coal fly-ash spill. We then tested whether Se concentrations differed with relative trophic position or relative carbon source. We did not observe a strong relationship between δ 15 N and Se concentration. Instead, selenium concentrations decreased with increasing δ 13 C among species. Therefore, in an assemblage of closely-related aquatic vertebrates, relative carbon source was a better predictor of Se bioaccumulation than was relative trophic position. -- Highlights: •Stable isotope results showed trophic separation among turtle species. •Selenium concentrations did not biomagnify with relative trophic position. •Selenium concentrations decreased with increasing δ 13 C among species. •Carbon source influenced Se bioaccumulation in an assemblage of related vertebrates. -- Stable isotope differences indicate that claw selenium concentrations differ among relative carbon sources, and not among relative trophic positions, in an assemblage of aquatic turtles

Various problems concerning radioactive waste disposal sites and parameters for their evaluation

International Nuclear Information System (INIS)

Fukui, Masami

1990-01-01

The present report first describes various methods used for low-level radioactive waste disposal in the U.S. and then discusses major factors affecting the parameters used for quantitative evaluation of the behavior of radioactive nuclides existing in the environment, focusing on the distribution coefficient which is assumed in a model widely used for such evaluation. Some problems encountered in applying these parameters to practical evaluation are also discussed together with further studies required in the future. The distribution coefficient varies with many physical, chemical and biological factors, and it may be unavoidable to rely on experiments with a simplified system in determining the effect of each factor separately. However, the values obtained from such experiments cannot be used as parameters to reflect the behaviors of these nuclides in real environments. They should be considered as such. Efforts should be made to develop techniques to obtain effective values for the distribution coefficient that properly reflect their behaviors in real environments near disposal sites or in far fields. (N.K.)

Geohydrologic problems at low-level radioactive waste disposal sites in the United States of America

International Nuclear Information System (INIS)

Fischer, J.N.; Robertson, J.B.

1984-01-01

Several commercial and US Department of Energy low-level radioactive waste disposal sites in the USA have not adequately contained the waste products. Studies of these sites indicate a number of causes for the problems, including water accumulation in filled trenches, breaches of trench cap integrity, erosion, high water table, hydrogeological complexity, flooding, complex leachate chemistry, and rapid radionuclide migration in groundwater. These problems can be avoided through the application of practical, comprehensive, and common sense earth-science guidelines discussed in this paper. (author)

Hybrid disposal systems and nitrogen removal in individual sewage disposal systems

Energy Technology Data Exchange (ETDEWEB)

Franks, A.L.

1993-06-01

The use of individual disposal systems in ground-water basins that have adverse salt balance conditions and/or geologically unsuitable locations, has become a major problem in many areas of the world. There has been much research in design of systems for disposal of domestic sewage. This research includes both hybrid systems for disposal of domestic sewage. This research includes both hybrid systems for disposal of the treated waste in areas with adverse geologic conditions and systems for the removal of nitrogen and phosphorus prior to percolation to the ground water. This paper outlines the history of development and rationale for design and construction of individual sewage disposal systems and describes the designs and limitations of the hybrid and denitrification units. The disposal systems described include Mounds, Evapotranspiration and Evapotranspiration/Infiltration systems. The denitrification units include those using methanol, sulfur and limestone, gray water and secondary treated wastewater for energy sources.

Scoping survey of perceived concerns, issues, and problems for near-surface disposal of FUSRAP waste

International Nuclear Information System (INIS)

Robinson, J.E.; Gilbert, T.L.

1982-12-01

This report is a scoping summary of concerns, issues, and perceived problems for near-surface disposal of radioactive waste, based on a survey of the current literature. Near-surface disposal means land burial in or within 15 to 20 m of the earth's surface. It includes shallow land burial (burial in trenches, typically about 6 m deep with a 2-m cap and cover) and some intermediate-depth land burial (e.g., trenches and cap similar to shallow land burial, but placed below 10 to 15 m of clean soil). Proposed solutions to anticipated problems also are discussed. The purpose of the report is to provide a better basis for identifying and evaluating the environmental impacts and related factors that must be analyzed and compared in assessing candidate near-surface disposal sites for FUSRAP waste. FUSRAP wastes are of diverse types, and their classification for regulatory purposes is not yet fixed. Most of it may be characterized as low-activity bulk solid waste, and is similar to mill tailings, but with somewhat lower average specific activity. It may also qualify as Class A segregated waste under the proposed 10 CFR 61 rules, but the parent radionuclides of concern in FUSRAP (primarily U-238 and Th-232) have longer half-lives than do the radionuclides of concern in most low-level waste. Most of the references reviewed deal with low-level waste or mill tailings, since there is as yet very little literature in the public domain on FUSRAP per se

Solving multi-objective facility location problem using the fuzzy analytical hierarchy process and goal programming: a case study on infectious waste disposal centers

Directory of Open Access Journals (Sweden)

Narong Wichapa

Full Text Available The selection of a suitable location for infectious waste disposal is one of the major problems in waste management. Determining the location of infectious waste disposal centers is a difficult and complex process because it requires combining social and environmental factors that are hard to interpret, and cost factors that require the allocation of resources. Additionally, it depends on several regulations. Based on the actual conditions of a case study, forty hospitals and three candidate municipalities in the sub-Northeast region of Thailand, we considered multiple factors such as infrastructure, geological and social & environmental factors, calculating global priority weights using the fuzzy analytical hierarchy process (FAHP. After that, a new multi-objective facility location problem model which combines FAHP and goal programming (GP, namely the FAHP-GP model, was tested. The proposed model can lead to selecting new suitable locations for infectious waste disposal by considering both total cost and final priority weight objectives. The novelty of the proposed model is the simultaneous combination of relevant factors that are difficult to interpret and cost factors, which require the allocation of resources. Keywords: Multi-objective facility location problem, Fuzzy analytic hierarchy process, Infectious waste disposal centers

Safety Problems of Disposal of Disused Sealed Sources in the Baldone Near Surface Repository

International Nuclear Information System (INIS)

Dreimanis, A.

2003-01-01

long-term storage; 3. To dispose only those sources capable to decay during functioning of disposal site. 4. To revise and update Waste Acceptance Criteria (WAC), especially for disused sealed sources. 5. To build a 5 m thick cap over the vaults. The activity related criteria and predisposal packing of DSS are presented. The problems and solutions for the construction of new storage and disposal spaces are discussed

Solidification/Stabilization of High Nitrate and Biodenitrified Heavy Metal Sludges with a Portland Cement/Flyash System

International Nuclear Information System (INIS)

Canonico, J.S.

1995-01-01

Pond 207C at Rocky Flats Environmental Technology Site (RFETS) contains process wastewaters characterized by high levels of nitrates and other salts, heavy metal contamination, and low level alpha activity. The purpose of this research was to investigate the feasibility of treating a high-nitrate waste, contaminated with heavy metals, with a coupled dewateriug and S/S process, as well as to investigate the effects of biodenitrification pretreatment on the S/S process. Pond 207C residuals served as the target waste. A bench-scale treatability study was conducted to demonstrate an S/S process that would minimize final product volume without a significant decrease in contaminant stabilization or loss of desirable physical characteristics. The process formulation recommended as a result a previous S/S treatability study conducted on Pond 207C residuals was used as the baseline formulation for this research. Because the actual waste was unavailable due to difficulties associated with radioactive waste handling and storage, a surrogate waste, of known composition and representative of Pond 207C residuals, was used throughout this research. The contaminants of regulatory concern added to the surrogate were cadmium, chromium, nickel, and silver. Product volume reduction was achieved by dewatering the waste prior to S/S treatment. The surrogate was dewatered by evaporation at 60 to 80 C to total solids contents from 43% to 78% by weight, and treated with Portland cement and fly ash. Two cement to flyash ratios were tested, 2:1 and 1:2, by weight. Contaminant leachability testing was conducted with a 0.5 water to pozzolan (the cement/flyash mixture) ratio and both cement to flyash ratios. Each product was tested for unconfined compressive strength (UCS) and for contaminant leachability by the Toxicity Characteristics Leaching Procedure (TCLP). At the highest solids content achieved by dewatering, 78% solids by weight, the predicted final waste form volume f or Pond 207C

INFLUENCE OF SILICEOUS AND CALCAREOUS FLY-ASHES ON PROPERTIES OF CEMENT MORTARS

Directory of Open Access Journals (Sweden)

Gabriela Monika Rutkowska

2016-09-01

Full Text Available Care of the environment in accordance with the principles of sustainable development introduces the possibility and need for waste recycling. Construction and building industries have the greatest potential for reuse of waste. The article presents the results of investigations of cement mortars – tests of compressive and tensile strength after 28 and 56 days of curing – for normative mortars and mortars containing fly ashes – calcareous and siliceous ash – in their composition. To make the samples, the Portland cement CEM I 32,5 R, 42,5R and natural aggregate with graining of 0–2 mm were used. Concrete with siliceous and calcareous admixtures was made in six lots where the ash was added in the quantity of 2%, 5%, 10% of the cement mass or the 2%, 5%, 10% of cement was replaced by ashes. After the tests, it was stated that the siliceous fly-ash admixture increases the compressive and bending strength in comparison to the mortars with the calcareous ash admixtures.

Crushing leads to waste disposal savings for FUSRAP

Energy Technology Data Exchange (ETDEWEB)

Darby, J. [Department of Energy, Oak Ridge, TN (United States)

1997-02-01

In this article the author discusses the application of a rock crusher as a means of implementing cost savings in the remediation of FUSRAP sites. Transportation and offsite disposal costs are at present the biggest cost items in the remediation of FUSRAP sites. If these debris disposal problems can be handled in different manners, then remediation savings are available. Crushing can result in the ability to handle some wastes as soil disposal problems, which have different disposal regulations, thereby permitting cost savings.

How a developing country is facing LLW disposal problem

International Nuclear Information System (INIS)

Huang, C.C.; Shao, Y.T.; Tsai, C.M.

1993-01-01

Taiwan is a small island which measures about 36,000 square kilometers with over 70% mountainous area. Today over 90% of low-level radioactive waste (LLW) is produced from six nuclear power units operated by the Taiwan Power Company (Taipower or TPC). The rest of the country's LLW is produced from medical, agricultural, industrial, educational and research programs. Due to the fact that over 90% of Taiwan's LLW is produced by Taipower, Taipower was designated by the Government to dispose of LLW for entire country. This paper will focus on the planning and implementation of the first phase. Through area screening and potential site evaluation, candidate sites will be selected based on currently available information and sites investigation. At the same time, the disposal methods will be evaluated in terms of safety, cost, and Taiwan's generic conditions of climate, geology, and topography. The conceptual design of the disposal method(s) will then be developed. Also, during site investigation, preliminary designs will be made

Waste disposal into the ground

Energy Technology Data Exchange (ETDEWEB)

Mawson, C A

1955-07-01

The establishment of an atomic energy project is soon followed by the production of a variety of radioactive wastes which must be disposed of safely, quickly and cheaply. Experience has shown that much more thought has been devoted to the design of plant and laboratories than to the apparently dull problem of what to do with the wastes, but the nature of the wastes which will arise from nuclear power production calls for a change in this situation. We shall not be concerned here with power pile wastes, but disposal problems which have occurred in operation of experimental reactors have been serious enough to show that waste disposal should be considered during the early planning stages. (author)

Radioactive waste products - suitability for final disposal

International Nuclear Information System (INIS)

Merz, E.; Odoj, R.; Warnecke, E.

1985-06-01

48 papers were read at the conference. Separate records are available for all of them. The main problem in radioactive waste disposal was the long-term sealing to prevent pollution of the biosphere. Problems of conditioning, acceptance, and safety measures were discussed. Final disposal models and repositories were presented. (PW) [de

Disposal of radioactive wastes

International Nuclear Information System (INIS)

Dlouhy, Z.

1982-01-01

This book provides information on the origin, characteristics and methods of processing of radioactive wastes, as well as the philosophy and practice of their storage and disposal. Chapters are devoted to the following topics: radioactive wastes, characteristics of radioactive wastes, processing liquid and solid radioactive wastes, processing wastes from spent fuel reprocessing, processing gaseous radioactive wastes, fixation of radioactive concentrates, solidification of high-level radioactive wastes, use of radioactive wastes as raw material, radioactive waste disposal, transport of radioactive wastes and economic problems of radioactive wastes disposal. (C.F.)

The scope and nature of the problem of high level nuclear waste disposal

International Nuclear Information System (INIS)

Jennekens, J.

1981-09-01

The disposal of high level nuclear waste poses a challenge to the Canadian technical and scientific communities, but a much greater challenge to government and industry leaders who must convince the public that the so-called 'problem' can be resolved by a pragmatic approach utilizing existing skills and knowledge. This paper outlines the objectives of radioactive waste management, the quantities of high level waste expected to be produced by the Canadian nuclear power program, the regulatory process which will apply and the government initiatives which have been and will be taken to ensure that the health, safety, security, and environmental interests of the public will be protected. (author)

The disposal of radioactive waste on land

Energy Technology Data Exchange (ETDEWEB)

None

1957-09-01

A committee of geologists and geophysicists was established by the National Academy of Sciences-National Research Council at the request of the Atomic Energy Commission to consider the possibilities of disposing of high level radioactive wastes in quantity within the continental limits of the United States. The group was charged with assembling the existing geologic information pertinent to disposal, delineating the unanswered problems associated with the disposal schemes proposed, and point out areas of research and development meriting first attention; the committee is to serve as continuing adviser on the geological and geophysical aspects of disposal and the research and development program. The Committee with the cooperation of the Johns Hopkins University organized a conference at Princeton in September 1955. After the Princeton Conference members of the committee inspected disposal installations and made individual studies. Two years consideration of the disposal problems leads to-certain general conclusions. Wastes may be disposed of safely at many sites in the United States but, conversely, there are many large areas in which it is unlikely that disposal sites can be found, for example, the Atlantic Seaboard. Disposal in cavities mined in salt beds and salt domes is suggested as the possibility promising the most practical immediate solution of the problem. In the future the injection of large volumes of dilute liquid waste into porous rock strata at depths in excess of 5,000 feet may become feasible but means of rendering, the waste solutions compatible with the mineral and fluid components of the rock must first be developed. The main difficulties, to the injection method recognized at present are to prevent clogging of pore space as the solutions are pumped into the rock and the prediction or control of the rate and direction of movement.

Disposal of Iodine-129

International Nuclear Information System (INIS)

Morgan, M.T.; Moore, J.G.; Devaney, H.E.; Rogers, G.C.; Williams, C.; Newman, E.

1978-01-01

One of the problems to be solved in the nuclear waste management field is the disposal of radioactive iodine-129, which is one of the more volatile and long-lived fission products. Studies have shown that fission products can be fixed in concrete for permanent disposal. Current studies have demonstrated that practical cementitious grouts may contain up to 18% iodine as barium iodate. The waste disposal criterion is based on the fact that harmful effects to present or future generations can be avoided by isolation and/or dilution. Long-term isolation is effective in deep, dry repositories; however, since penetration by water is possible, although unlikely, release was calculated based on leach rates into water. Further considerations have indicated that sea disposal on or in the ocean floor may be a more acceptable alternative

Estimating the burden of illness in an Ontario community with untreated drinking water and sewage disposal problems.

Science.gov (United States)

Chambers, L W; Shimoda, F; Walter, S D; Pickard, L; Hunter, B; Ford, J; Deivanayagam, N; Cunningham, I

1989-01-01

The Hamilton-Wentworth regional health department was asked by one of its municipalities to determine whether the present water supply and sewage disposal methods used in a community without piped water and regional sewage disposal posed a threat to the health of its residents. Three approaches were used: assessments by public health inspectors of all households; bacteriological and chemical analyses of water samples; and completion of a specially designed questionnaire by residents in the target community and a control community. 89% of the 227 residences in the target community were found to have a drinking water supply that, according to the Ministry of Environment guidelines, was unsafe and/or unsatisfactory. According to on-site inspections, 32% of households had sewage disposal problems. Responses to the questionnaire revealed that the target community residents reported more symptoms associated with enteric infections due to the water supply. Two of these symptoms, diarrhea and stomach cramps, had a relative risk of 2.2 when compared to the control community (p less than 0.05). The study was successfully used by the municipality to argue for provincial funding of piped water.

Sewage sludge disposal in Austria

International Nuclear Information System (INIS)

Koch, F.

1997-01-01

Sewage systems serve about 70% of the Austrian population, producing 6 million m 3 of sewage sludge per year with a dry matter content of 4-5%. At present about 52% of this sludge is disposed of in land fills, 33% is incinerated, and only about 15 % is used in agriculture. Although agricultural utilization is becoming increasingly important, several problems, especially those related to public opinion, need to be resolved before increased use will be possible. In this paper, wastewater treatment and sewage-sludge production in Austria, and problems associated with sludge disposal are discussed. (author)

The trapping of fly-ash particles in the surface layers of Sphagnum-dominated peat

International Nuclear Information System (INIS)

Punning, J.-M.; Alliksaar, T.

1997-01-01

The movement of fly-ash particles in a sequence of Sphagnum moss was studied in laboratory experiments and field investigations. Fly ash was obtained from the electrostatic precipitators of the Estonian Thermal Power Plant operating on oil shale. The data obtained in the laboratory show that only 0.8% of particles, placed on the surface of a 6-10 cm thick Sphagnum layer, were washed out with water (700-750 mm) during the 241 days of the experiment. The majority of added particles were fixed in the upper part (90% in 1-3 cm) of the moss layer. A SEM study indicates that sorption is slightly species-dependent due to the micromorphological parameters of the Sphagnum species. The storage of particles by Sphagnum mosses allows the use of natural sequences to study the history of atmospheric pollution. The distribution of particles in the upper part of moss layers in Viru Bog (50 km east of Tallinn, North Estonia) shows good agreement with the known air pollution history in Tallinn. 13 refs., 6 figs., 2 tabs

Cost effective disposal of whey

Energy Technology Data Exchange (ETDEWEB)

Zall, R R

1980-01-01

Means of reducing the problem of whey disposal are dealt with, covering inter alia the pre-treatment of cheese milk e.g., by ultrafiltration to lower the whey output, utilization of whey constituents, use of liquid whey for feeding, fermenting whey to produce methane and alcohol, and disposal of whey by irrigation of land or by purification in sewage treatment plants.

Long-Term Behaviors of the OPC Concrete with Fly-ash and Type V Concrete Applied on Reactor Containment Building

International Nuclear Information System (INIS)

Yoon, Eui Sik; Lee, Hee Taik; Paek, Yong Lak; Park, Young Soo

2010-01-01

The prestressed concrete has been used extensively in the construction of Reactor Containment Buildings (RCBs) in Korea in order to strengthen the RCBs and at the same time, prevent the release of radiation due to the Design Basis Accident and Design Basis Earthquake. It is well known that the prestressed concrete loses its prestressing force over the age, and the shrinkage and creep of the concrete significantly contributes to these long term prestressing losses. In this study, an evaluations of long term behaviors of the concrete such as creep and shrinkage have been performed for two types of concretes : Ordinary Portland Cement containing fly-ash used for the Shin- Kori 1 and 2 NPP and Type V cement used for the Ul- Chin 5 and 6 NPP

Long-Term Behaviors of the OPC Concrete with Fly-ash and Type V Concrete Applied on Reactor Containment Building

Energy Technology Data Exchange (ETDEWEB)

Yoon, Eui Sik; Lee, Hee Taik; Paek, Yong Lak [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of); Park, Young Soo [Korea Hydro and Nuclear Power Co., Busan (Korea, Republic of)

2010-10-15

The prestressed concrete has been used extensively in the construction of Reactor Containment Buildings (RCBs) in Korea in order to strengthen the RCBs and at the same time, prevent the release of radiation due to the Design Basis Accident and Design Basis Earthquake. It is well known that the prestressed concrete loses its prestressing force over the age, and the shrinkage and creep of the concrete significantly contributes to these long term prestressing losses. In this study, an evaluations of long term behaviors of the concrete such as creep and shrinkage have been performed for two types of concretes : Ordinary Portland Cement containing fly-ash used for the Shin- Kori 1 and 2 NPP and Type V cement used for the Ul- Chin 5 and 6 NPP

Interim storage is not long-term disposal

International Nuclear Information System (INIS)

Vincenti, J.R.

1994-01-01

Starting in June 30, 1994 South Carolina enforced an embargo on regular shipments of low-level radioactive waste to the Barnwell repository. The failure of 31 states and their respective compacts to provide access to a long-term disposal facility as stipulated by the low-level radioactive Waste Policy Act of 1980 promotes waste disposal gridlock and anticipates another waste disposal crisis. This article discusses the problem using the following topics: Appalachian Compact Users of Radioactive Isotopes (ACURI) Association's interest; the problem of denial of access to Barnwell; pro and contra interim storage; vital services and benefits at risk; issues at the ACURI meeting; nobel Prize winners use radioactive materials; if perception is reality, politics is prevalent

Disposal of high level radioactive wastes in geological formations

International Nuclear Information System (INIS)

Martins, L.A.M.; Carvalho Bastos, J.P. de

1978-01-01

The disposal of high-activity radioactive wastes is the most serious problem for the nuclear industry. Among the solutions, the disposal of wastes in approriated geological formations is the most realistic and feasible. In this work the methods used for geological disposal, as well as, the criteria, programs and analysis for selecting a bite for waste disposal are presented [pt

Problems experiences with the construction of cement and lime stabilized layers and working solutions for these problems

CSIR Research Space (South Africa)

Botha, PB

2005-10-01

Full Text Available Stabilized layers are used extensively in South-Africa in the construction of roads. The layers are usually stabilized with hydrated road lime, cement, slag, fly-ash, bitumen emulsion, foamed asphalt or a combination of several of these agents...

Risk analysis of geological disposal of radioactive waste

International Nuclear Information System (INIS)

Girardi, F.; de Marsily, G.; Weber, J.

1980-01-01

The problems of risk analysis of geological disposal of radioactive waste are briefly summarized. Several characteristics, such as the very long time span considered, make it rather unique among the problems of modern society. The safety of nuclear waste disposal in geological formations is based on several barriers, natural and man-made, which prevent disposed radionuclides from reaching the biosphere. They include a) the physico-chemical form of conditioned waste, b) the waste container, c) the geological isolation, d) buffering and backfilling materials, radionuclide retention in the geosphere and e) environmental dilution and isolation processes. The knowledge available on each barrier and its modelling is reviewed. Specific disposal strategies in clay, granite and salt formations are considered, outlining the performance of the barriers in each particular strategy, and results obtained in preliminary evaluations

Panel session: Disposal of HLW - ready for implementation

International Nuclear Information System (INIS)

Heremans, R.; Come, B.; Barbreau, A.; Girardi, F.

1986-01-01

The paper is a report of a panel session at the European Community conference on radioactive waste management and disposal, Luxembourg 1985, concerning the safe and long-term disposal of high-activity and long-lived waste. The subjects discussed include: geological barriers including deep sea-bed sediments, engineered barriers, technological problems (repository construction, waste emplacement, backfilling and sealing), safety analysis, performance assessment of disposal system components, and finally institutional, legal and financial aspects of geological disposal. (U.K.)

25 CFR 91.13 - Health, sanitation, and sewerage disposal.

Science.gov (United States)

2010-04-01

... 25 Indians 1 2010-04-01 2010-04-01 false Health, sanitation, and sewerage disposal. 91.13 Section... INDIAN VILLAGES, OSAGE RESERVATION, OKLAHOMA § 91.13 Health, sanitation, and sewerage disposal. Health, sanitation, and sewerage disposal problems within the village reserves shall be subject to and controlled by...

radioactive waste disposal standards abroad

International Nuclear Information System (INIS)

Lu Yan; Xin Pingping; Wu Jian; Zhang Xue

2012-01-01

With the world focus on human health and environmental protection, the problem of radioactive waste disposal has gradually become a global issue, and the focus of attention of public. The safety of radioactive waste disposal, is not only related to human health and environmental safety, but also an important factor of affecting the sustainable development of nuclear energy. In recent years the formulation of the radioactive waste disposal standards has been generally paid attention to at home and abroad, and it has made great progress. In China, radioactive waste management standards are being improved, and there are many new standards need to be developed. The revised task of implement standards is very arduous, and there are many areas for improvement about methods and procedures of the preparation of standards. This paper studies the current situation of radioactive waste disposal standards of the International Atomic Energy Agency, USA, France, Britain, Russia, Japan, and give some corresponding recommendations of our radioactive waste disposal standards. (authors)

High-level radioactive waste disposal problem in Russia

International Nuclear Information System (INIS)

Velichkin, Vasily I.

1999-01-01

This presentation on radioactive waste management in Russia discusses criteria for the selection of disposal sites, how the various types of waste should be contained and stored, and gives a list showing the liable owner, type, volume, activity and storage place of the present amount of radioactive waste. The bulk of this waste, in volume and radioactivity, is at the enterprises of Minatom of the Russian Federation

High-level waste processing and disposal

International Nuclear Information System (INIS)

Crandall, J.L.; Krause, H.; Sombret, C.; Uematsu, K.

1984-01-01

The national high-level waste disposal plans for France, the Federal Republic of Germany, Japan, and the United States are covered. Three conclusions are reached. The first conclusion is that an excellent technology already exists for high-level waste disposal. With appropriate packaging, spent fuel seems to be an acceptable waste form. Borosilicate glass reprocessing waste forms are well understood, in production in France, and scheduled for production in the next few years in a number of other countries. For final disposal, a number of candidate geological repository sites have been identified and several demonstration sites opened. The second conclusion is that adequate financing and a legal basis for waste disposal are in place in most countries. Costs of high-level waste disposal will probably add about 5 to 10% to the costs of nuclear electric power. The third conclusion is less optimistic. Political problems remain formidable in highly conservative regulations, in qualifying a final disposal site, and in securing acceptable transport routes

Disposal of radioactive waste

Energy Technology Data Exchange (ETDEWEB)

NONE

1960-01-15

The problem of disposal can be tackled in two ways: the waste can be diluted and dispersed so that the radiation to which any single individual would be subjected would be negligible, or it can be concentrated and permanently isolated from man and his immediate environment. A variety of methods for the discharge of radioactive waste into the ground were described at the Monaco conference. They range from letting liquid effluent run into pits or wells at appropriately chosen sites to the permanent storage of high activity material at great depth in geologically suitable strata. Another method discussed consists in the incorporation of high level fission products in glass which is either buried or stored in vaults. Waste disposal into rivers, harbours, outer continental shelves and the open sea as well as air disposal are also discussed. Many of the experts at the Monaco conference were of the view that most of the proposed, or actually applied, methods of waste disposal were compatible with safety requirements. Some experts, felt that certain of these methods might not be harmless. This applied to the possible hazards of disposal in the sea. There seemed to be general agreement, however, that much additional research was needed to devise more effective and economical methods of disposal and to gain a better knowledge of the effects of various types of disposal operations, particularly in view of the increasing amounts of waste material that will be produced as the nuclear energy industry expands

User's guide to the 'DISPOSALS' model

International Nuclear Information System (INIS)

Groom, M.S.; James, A.R.; Laundy, R.S.

1984-03-01

This report provides a User's Guide to the 'DISPOSALS' computer model and includes instructions on how to set up and run a specific problem together with details of the scope, theoretical basis, data requirements and capabilities of the model. The function of the 'DISPOSALS' model is to make assignments of nuclear waste material in an optimum manner to a number of disposal sites each subject to a number of constraints such as limits on the volume and activity. The user is able to vary the number of disposal sites, the range and limits of the constraints to be applied to each disposal site and the objective function for optimisation. The model is based on the Linear Programming technique and uses CAP Scientific's LAMPS and MAGIC packages. Currently the model has been implemented on CAP Scientific's VAX 11/750 minicomputer. (author)

Electrochemical recycling of metals from slags and flyash; Elektrokemisk metallaatervinning ur slagg och flygaska

Energy Technology Data Exchange (ETDEWEB)

Bjoerefors, Fredrik; Ulrich, Christian (Linkoepings Univ., Linkoeping (Sweden))

2009-11-15

The main objective with this project was to explore the possibility to employ electrochemical methods to reduce the metal content in waste products (slag and fly ash) from waste incineration facilities. The basic idea was to first dissolve the waste products in acid, and then to reduce and deposit as much as possible of the metal ions onto an electrode surface. Experiments were further performed to determine to which extent the deposited metals could be reoxidized into a separate and clean acidic solution (with metal recycling in mind). Parameters like the pH, deposition potential and time, and electrode area were investigated. The results clearly indicated that it to a large extent was possible to decrease the metal concentration in the slag and flyash, more than 90% of the copper ions could for example be extracted from the initial acidic slurry. However, a very strong acid was necessary to dissolve the waste products, and it was further necessary to increase the pH in this solution prior to the electrochemical reduction. In the report, some suggestions for future activities at a larger scale will also be addressed

Nuclear waste disposal technology for Pacific Basin countries

International Nuclear Information System (INIS)

Langley, R.A. Jr.; Brothers, G.W.

1981-01-01

Safe long-term disposal of nuclear wastes is technically feasible. Further technological development offers the promise of reduced costs through elimination of unnecessary conservatism and redundance in waste disposal systems. The principal deterrents to waste disposal are social and political. The issues of nuclear waste storage and disposal are being confronted by many nuclear power countries including some of the Pacific Basin nuclear countries. Both mined geologic and subseabed disposal schemes are being developed actively. The countries of the Pacific Basin, because of their geographic proximity, could benefit by jointly planning their waste disposal activities. A single repository, of a design currently being considered, could hold all the estimated reprocessing waste from all the Pacific Basin countries past the year 2010. As a start, multinational review of alterntive disposal schemes would be beneficial. This review should include the subseabed disposal of radwastes. A multinational review of radwaste packaging is also suggested. Packages destined for a common repository, even though they may come from several countries, should be standardized to maximize repository efficiency and minimize operator exposure. Since package designs may be developed before finalization of a repository scheme and design, the packages should not have characteristics that would preclude or adversely affect operation of desirable repository options. The sociopolitical problems of waste disposal are a major deterrent to a multinational approach to waste disposal. The elected representatives of a given political entity have generally been reluctant to accept the waste from another political entity. Initial studies would, nevertheless, be beneficial either to a common solution to the problem, or to aid in separate solutions

Recent activity on disposal of uranium waste

International Nuclear Information System (INIS)

Fujiwara, Noboru

1999-01-01

The concept on the disposal of uranium waste has not been discussed in the Atomic Energy Commission of Japan, but the research and development of it are carried out in the company and agency which are related to uranium waste. In this paper, the present condition and problems on disposal of uranium waste were shown in aspect of the nuclear fuel manufacturing companies' activity. As main contents, the past circumstances on the disposal of uranium waste, the past activity of nuclear fuel manufacturing companies, outline and properties of uranium waste were shown, and ideas of nuclear fuel manufacturing companies on the disposal of uranium waste were reported with disposal idea in the long-term program for development and utilization of nuclear energy. (author)

The problem of nitrogen disposal in the obese

OpenAIRE

Alemany, Marià, 1946-

2012-01-01

Amino-N is preserved because of the scarcity and nutritional importance of protein. Excretion requires its conversion to ammonia, later incorporated into urea. Under conditions of excess dietary energy, the body cannot easily dispose of the excess amino-N against the evolutively adapted schemes that prevent its wastage; thus ammonia and glutamine formation (and urea excretion) are decreased. High lipid (and energy) availability limits the utilisation of glucose, and high glucose spares the pr...

Status report on the disposal of radioactive wastes

Energy Technology Data Exchange (ETDEWEB)

Culler, F.L. Jr.; McLain, S. (comps.)

1957-06-25

A comprehensive survey of waste disposal techniques, requirements, costs, hazards, and long-range considerations is presented. The nature of high level wastes from reactors and chemical processes, in the form of fission product gases, waste solutions, solid wastes, and particulate solids in gas phase, is described. Growth predictions for nuclear reactor capacity and the associated fission product and transplutonic waste problem are made and discussed on the basis of present knowledge. Biological hazards from accumulated wastes and potential hazards from reactor accidents, ore and feed material processing, chemical reprocessing plants, and handling of fissionable and fertile material after irradiation and decontamination are surveyed. The waste transportation problem is considered from the standpoints of magnitude of the problem, present regulations, costs, and cooling periods. The possibilities for ultimate waste management and/or disposal are reviewed and discussed. The costs of disposal, evaporation, storage tanks, and drum-drying are considered.

Treatment and disposal of radioactive wastes and countermeasures

International Nuclear Information System (INIS)

Nomura, Kiyoshi

1990-01-01

The treatment and disposal of radioactive wastes are one of important subjects, together with the development of dismantling techniques accompanying the decommissioning measures for nuclear power plants and the development of reprocessing techniques for nuclear fuel cycle. About 25 years have elapsed since the beginning of commercial nuclear power generation in 1966, and the time that the solution of the problems of waste treatment and disposal must be tackled on full scale has come. The features and the amount of generation of radioactive wastes, the way of thinking on the treatment and disposal, and the present status of the treatment and disposal are outlined. For securing the stable supply of energy and solving the environmental problem of the earth such as acid rain and warming, nuclear power generation accomplishes important roles. The objective of waste treatment is based on the way of thinking of 'as low as reasonably achievable (ALARA)'. The radioactive wastes are classified into alpha waste and beta-gamma waste. The present status of RI wastes, the techniques of treating radioactive wastes, the nuclide separation, extinction treatment and the disposal in strata of high level radioactive wastes and the disposal of low level wastes are reported. (K.I.)

How Hungary is Facing Waste Disposal Problem

International Nuclear Information System (INIS)

Ormai, P.; Frigyesi, F.; Gresits, I.; Solymosi, J.; Vincze, A.

1999-01-01

Management of radioactive waste of nuclear power plant origin comprises two main tasks: management of the high-level (spent fuel) and the low-and intermediate-level waste (LILW). With a plan to start operation of a repository for low-and intermediate-level waste (LILW) at the beginning of the next century, a site investigation programme was started in 1993. The site selection procedure. Between 1993-1995 some 300 geological objects were identified as potentially suitable for either near surface or tunnel-type disposal. The first stage of the site exploration has been performed and the decision on the continuation of the programme is due to by the end of 1998

Inter- and transdisciplinarity as a precondition for final nuclear waste disposal

International Nuclear Information System (INIS)

Chaudry, Saleem; Kuppler, Sophie; Smeddinck, Ulrich

2016-01-01

Searching for solutions for solving environmental problems, dissolves the boundaries between the several scientific disciplines. The disposal of radioactive waste requires such interdisciplinary solutions. A problem is described, which generates new problems, if one is solved. The interdisciplinary cooperation for the evaluation of a disposal solution is described. The point of view is a theoretical approach and a transdisciplinary combination of science and the public.

Nuclear waste disposal: regional options for the Western Pacific

International Nuclear Information System (INIS)

Childs, I.

1985-01-01

The disposal of nuclear waste is a complex environmental problem involving the technology of containing a radiation hazard and the political problem of finding an acceptable site for a hazardous waste facility. The focus of discussion here is the degree to which Western Pacific countries are committed to nuclear power as an energy source, and the political and economic interdependencies in the region which will influence waste disposal options

Probabilistic safety assessment in radioactive waste disposal

International Nuclear Information System (INIS)

Robinson, P.C.

1987-07-01

Probabilistic safety assessment codes are now widely used in radioactive waste disposal assessments. This report gives an overview of the current state of the field. The relationship between the codes and the regulations covering radioactive waste disposal is discussed and the characteristics of current codes is described. The problems of verification and validation are considered. (author)

ROCTECtm STABILIZATION TREATMENT OF WERF ASH

Energy Technology Data Exchange (ETDEWEB)

Paul A. Lessing; William J. Quapp; Gary Renlund; Bob Clark; Colin Hundley; James Cornwell; Dave Schlier; John Bulko; Gene Pollack

1998-10-01

The objective of this project is to demonstrate a process to stabilize mixed waste flyash generated by the combustion of mixed waste at the Idaho National Engineering & Environmental Laboratory's (INEEL's) Waste Experimental Reduction Facility (WERF) incinerator such that it will meet Resource Conservation and Recovery Act (RCRA) Land Disposal Restrictions (LDRs) Universal Treatment Standards.

Reprocessing and disposal of used lubricating and process materials. requirements, problems, and solution methods

Energy Technology Data Exchange (ETDEWEB)

Matzke, U D

1978-02-01

A discussion covers West German laws concerning used oil disposal and re-refining (316,000 tons were reprocessed in 1976); disposal of sulfuric acid resins or tar and fuller's earth containing mineral oils by solidification (with added lime, alkali ash, clay, etc.) or pyrolysis; disposal of rolling mill scale and sludge containing oil and grease by rolling with a solid carbonaceous material and processing to high-grade sponge iron; and the breaking of oil-water emulsions.

Technical reliability of geological disposal for high-level radioactive wastes in Japan. The second progress report. An extra issue: background of the geological disposal

International Nuclear Information System (INIS)

1999-11-01

Based on the Advisory Committee Report on Nuclear Fuel Cycle Backend Policy submitted to the Japanese Government in 1997, JNC documents the progress of research and development program in the form of the second progress report (the first one published in 1992). It summarizes an evaluation of the technical reliability and safety of the geological disposal concept for high-level radioactive wastes (HLW) in Japan. The present document, an extra issue of the progress report, was prepared for the expected readers of the report to have background information on the geological disposal. Thus it gives information about (1) generation of high-level radioactive wastes, (2) history of plans proposed for HLW disposal in Japan, and (3) procedure until the geological disposal plan is finally adopted and basic future schedules. It further discusses on such problems in HLW treatment and disposal, as for example a problem of reliable safety for a very long period. (Ohno, S.)

Revised user's guide to the 'DISPOSALS' model

International Nuclear Information System (INIS)

Laundy, R.S.; James, A.R.; Groom, M.S.; LeJeune, S.R.

1985-04-01

This report provides a User's Guide to the 'DISPOSALS' computer model and includes instructions on how to set up and run a specific problem together with details of the scope, theoretical basis, data requirements and capabilities of the model. The function of the 'DISPOSALS' model is to make assignments of nuclear waste material in an optimum manner to a number of disposal sites each subject to a number of constraints such as limits on the volume and activity. The user is able to vary the number of disposal sites, the range and limits of the constraints to be applied to each disposal site and the objective function for optimisation. The model is based on the Linear Programming technique and uses CAP Scientific's LAMPS and MAGIC packages. Currently the model has been implemented on CAP Scientific's VAX 11/750 minicomputer. (author)

How the oil companies look at CO2 separation and disposal

International Nuclear Information System (INIS)

Kaarstad, O.

2001-01-01

Separation and disposal of CO 2 is a new complex problem, and we should not be surprised that the technology available today does not solve all our problems. Neither should we be surprised that politicians, environmentalists, industry leaders and the general public have problems to digest the idea of underground disposal of CO 2 . The main challenges we are facing are: Reducing the investment and operational costs for CO 2 -separation; Finding solutions that do not create new environmental problems; Finding cheaper methods for transport of medium volumes of C= 2 over long distances; Keep informing the public of the pros and cons of underground disposal; Finding good transition strategies; Look for ways of cooperation between industry, authorities and research organizations to manage the transition period, including adaption of legislation to the new situation

Landfill disposal risk assessment

International Nuclear Information System (INIS)

Mininni, G.; Passino, R.; Spinosa, L.

1993-01-01

Landfill disposal is the most used waste disposal system in Italy, due to its low costs and also to the great opposition of populations towards new incineration plants and the adjustment of the existing ones. Nevertheless, landfills may present many environmental problems as far as leachate and biogas are concerned directly influencing water, air and soil. This paper shows the most important aspects to be considered for a correct evaluation of environmental impacts caused by a landfill of urban wastes. Moreover, detection systems for on site control of pollution phenomena are presented and some measures for an optimal operation of a landfill are suggested

Seabed disposal of high-level nuclear wastes: an alternative viewpoint

International Nuclear Information System (INIS)

Glasby, G.P.

1985-01-01

Various comments on a published article on subseabed disposal of nuclear wastes are presented. These include the scale of the proposed operation, the technical problems of canister retrievability, the feasibility of the free-fall penetrometer disposal method, canister lifetime, the possible contravention of the 1972 London Dumping Convention and land-based geological repositories as an alternative method of disposal. (author)

High-level nuclear waste disposal

International Nuclear Information System (INIS)

Burkholder, H.C.

1985-01-01

The meeting was timely because many countries had begun their site selection processes and their engineering designs were becoming well-defined. The technology of nuclear waste disposal was maturing, and the institutional issues arising from the implementation of that technology were being confronted. Accordingly, the program was structured to consider both the technical and institutional aspects of the subject. The meeting started with a review of the status of the disposal programs in eight countries and three international nuclear waste management organizations. These invited presentations allowed listeners to understand the similarities and differences among the various national approaches to solving this very international problem. Then seven invited presentations describing nuclear waste disposal from different perspectives were made. These included: legal and judicial, electric utility, state governor, ethical, and technical perspectives. These invited presentations uncovered several issues that may need to be resolved before high-level nuclear wastes can be emplaced in a geologic repository in the United States. Finally, there were sixty-six contributed technical presentations organized in ten sessions around six general topics: site characterization and selection, repository design and in-situ testing, package design and testing, disposal system performance, disposal and storage system cost, and disposal in the overall waste management system context. These contributed presentations provided listeners with the results of recent applied RandD in each of the subject areas

Hazardous waste disposal sites: Report 2

International Nuclear Information System (INIS)

1979-12-01

Arkansas, like virtually every other state, is faced with a deluge of hazardous waste. There is a critical need for increased hazardous waste disposal capacity to insure continued industrial development. Additionally, perpetual maintenance of closed hazardous waste disposal sites is essential for the protection of the environment and human health. Brief descriptions of legislative and regulatory action in six other states are provided in this report. A report prepared for the New York State Environmental Facilities Corp. outlines three broad approaches states may take in dealing with their hazardous waste disposal problems. These are described. State assistance in siting and post-closure maintenance, with private ownership of site and facility, appears to be the most advantageous option

High-Level Radioactive Waste: Safe Storage and Ultimate Disposal.

Science.gov (United States)

Dukert, Joseph M.

Described are problems and techniques for safe disposal of radioactive waste. Degrees of radioactivity, temporary storage, and long-term permanent storage are discussed. Included are diagrams of estimated waste volumes to the year 2000 and of an artist's conception of a permanent underground disposal facility. (SL)

Research and development for treatment and disposal technologies of TRU waste

International Nuclear Information System (INIS)

Kamei, Gento; Honda, Akira; Mihara, Morihiro; Oda, Chie; Murakami, Hiroshi; Masuda, Kenta; Yamaguchi, Kohei; Nakanishi, Hiroshi; Sasaki, Ryoichi; Ichige, Satoru; Takahashi, Kuniaki; Meguro, Yoshihiro; Yamaguchi, Hiromi; Aoyama, Yoshio

2007-09-01

After the publication of the 2nd progress report of geological disposal of TRU waste in Japan, policy and general scheme of future study for the waste disposal in Japan was published by ANRE and JAEA. This annual report summarized aim and progress of individual problem, which was assigned into JAEA in the published policy and general scheme. The problems are as follows; characteristics of TRU waste and its geologic disposal, treatment and waste production, quality control and inspection methodology for waste, mechanical analysis of near-field, data acquisition and preparation on radionuclides migration, cementitious material transition, bentonite and rock alteration in alkaline solution, nitrate effect, performance assessment of the disposal system and decomposition of nitrate as an alternative technology. (author)

The problem of nitrogen disposal in the obese.

Science.gov (United States)

Alemany, Marià

2012-06-01

Amino-N is preserved because of the scarcity and nutritional importance of protein. Excretion requires its conversion to ammonia, later incorporated into urea. Under conditions of excess dietary energy, the body cannot easily dispose of the excess amino-N against the evolutively adapted schemes that prevent its wastage; thus ammonia and glutamine formation (and urea excretion) are decreased. High lipid (and energy) availability limits the utilisation of glucose, and high glucose spares the production of ammonium from amino acids, limiting the synthesis of glutamine and its utilisation by the intestine and kidney. The amino acid composition of the diet affects the production of ammonium depending on its composition and the individual amino acid catabolic pathways. Surplus amino acids enhance protein synthesis and growth, and the synthesis of non-protein-N-containing compounds. But these outlets are not enough; consequently, less-conventional mechanisms are activated, such as increased synthesis of NO∙ followed by higher nitrite (and nitrate) excretion and changes in the microbiota. There is also a significant production of N(2) gas, through unknown mechanisms. Health consequences of amino-N surplus are difficult to fathom because of the sparse data available, but it can be speculated that the effects may be negative, largely because the fundamental N homeostasis is stretched out of normalcy, forcing the N removal through pathways unprepared for that task. The unreliable results of hyperproteic diets, and part of the dysregulation found in the metabolic syndrome may be an unwanted consequence of this N disposal conflict.

Feasible research on VLLW disposal in control area of nuclear installation

International Nuclear Information System (INIS)

Kong Jinsong; Guo Weiqun

2013-01-01

Based on the basic requirements on the VLLW landfill disposal specified by the national codes and standards, a on-site disposal of VLLW in the control area of nuclear installation was proposed. A detail analysis of the advantages and disadvantages about the disposal method and the problem to be solved were described. Results showed that the on-site disposal of VLLW in the control area of nuclear installation was feasible in practice. (authors)

Slag-based saltstone formulations

International Nuclear Information System (INIS)

Langton, C.A.

1987-08-01

Approximately 400 x 10 6 L of low-level alkaline salt solution will be treated at the Savannah River Plant (SRP) Defense Waste Processing Facility (DWPF) prior to disposal in concrete vaults at SRP. Treatment involves removal of Cs + and Sr +2 , followed by solidification and stabilization of potential contaminants in saltstone, a hydrated ceramic wasteform. Chromium, technetium, and nitrate releases from saltstone can be significantly reduced by substituting hydraulic blast furnace slag for portland cement in the formulation designs. Slag-based mixes are also compatible with the Class F flyash used in saltstone as a functional extender to control heat of hydration and reduce permeability. (Class F flyash is also locally available at SRP.) A monolithic wasteform is produced by the hydration of the slag and flyash. Soluble ion release (NO 3- ) is controlled by the saltstone microstructure. Chromium and technetium are less leachable from slag mixes because these species are chemically reduced to a lower valence state by ferrous iron in the slag and are precipitated as relatively insoluble phases, such as Cr(OH) 3 and TcO 2 . 3 refs., 3 figs., 2 tabs

Radioactive waste disposal and constitution

International Nuclear Information System (INIS)

Stober, R.

1983-01-01

The radioactive waste disposal has many dimensions with regard to the constitutional law. The central problem is the corret delimitation between adequate governmental precautions against risks and or the permitted risk which the state can impose on the citizen, and the illegal danger which nobody has to accept. The solution requires to consider all aspects which are relevant to the constitutional law. Therefore, the following analysis deals not only with the constitutional risks and the risks of the nuclear energy, but also with the liberal, overall-economic, social, legal, and democratic aspects of radioactive waste disposal. (HSCH) [de

Offshore disposal of oil-based drilling fluid waste

International Nuclear Information System (INIS)

Malachosky, E.; Shannon, B.E.; Jackson, J.E.

1991-01-01

Offshore drilling operations in the Gulf of Mexico may use oil-based drilling fluids to mitigate drilling problems. The result is the generation of a significant quantity of oily cuttings and mud. The transportation of this waste for onshore disposal is a concern from a standpoint of both personnel safety and potential environmental impact. A process for preparing a slurry of this waste and the subsequent disposal of the slurry through annular pumping has been put into use by ARCO Oil and Gas Company. The disposal technique has been approved by the Minerals Management Service (MMS). The slurried waste is displaced down a casing annulus into a permeable zone at a depth below the surface casing setting depth. The annular disposal includes all cuttings and waste oil mud generated during drilling with oil-based fluids. This disposal technique negates the need for cuttings storage on the platform, transportation to shore, and the environmental effects of onshore surface disposal. The paper describes the environmental and safety concerns with onshore disposal, the benefits of annular disposal, and the equipment and process used for the preparation and pumping of the slurry

Geology of high-level nuclear waste disposal

International Nuclear Information System (INIS)

Roxburgh, I.S.

1988-01-01

The concept of geological disposal is set out by describing the major rock types in terms of their ability to isolate high-level nuclear waste. The advantages and problems posed by particular rock formations are explored and the design and construction of geological repositories is considered, along with the methods used to estimate their safety. It gives special consideration to the use of sea-covered rock and sediment as well as the on-land situation. Throughout the book the various principles and problems inherent in geological disposal are explained and illustrated by reference to a multitude of European and North American case studies, backed up by a large number of tables, figures and an extensive bibliography

Radioactive waste disposal into the ground

International Nuclear Information System (INIS)

1965-01-01

Disposal into ground has sometimes proved to be an expedient and simple method. Where ground disposal has become an established practice, the sites have so far been limited to those remote from population centres; but in other respects, such as in climate and soil conditions, their characteristics vary widely. Experience gained at these sites has illustrated the variety of problems in radioactive waste migration and the resulting pollution and environmental radiation levels that may reasonably be anticipated at other sites, whether remote from population centres or otherwise.

In-situ grouting of the low-level radioactive waste disposal silos at ORNL's Solid Waste Storage Area Six

International Nuclear Information System (INIS)

Francis, C.W.; Farmer, C.D.; Stansfield, R.G.

1993-07-01

At Oak Ridge National Laboratory (ORNL), one method of solid low-level radioactive waste disposal has been disposed of in below-grade cylindrical concrete silos. Located in Solid Waste Storage Area 6 (SWSA 6), each silo measures 8 ft in diameter and 20 ft deep. Present day operations involve loading the silos with low-level radioactive waste and grouting the remaining void space with a particulate grout of low viscosity. Initial operations involving the disposal of wastes into the below-grade silos did not include the grouting process. Grouting was stated as a standard practice (in late 1988) after discovering that ∼75% of the silos accumulated water in the bottom of the silos in the ∼2 years after capping. Silo water (leachate) contained a wide range of types and concentrations of radionuclides. The migration of contaminated leachate out of the silo into adjoining soil and groundwater was considered to be a serious environmental concern. This report describes how a specially designed particulate-base grout was used to grout 54 silos previously filled with low-level radioactive waste. Grouting involved three steps: (1) silo preparation, (2) formulation and preparation of the grout mixture, and (3) injection of the grout into the silos. Thirty-five of the 54 silos grouted were equipped with a 3-in.-diam Polyvinyl Chloride (PVC) pipe used to monitor water levels in the silos. A method for rupturing the bottom section of these PVC wells was developed so that grout could be pumped to the bottom of those silos. Holes (2-in. diam) were drilled through the ∼18 in. thick concrete to fill the remaining 19 wells without the PVC monitoring wells. The formulation of grout injected into the silos was based on a Portland Type I cement, flyash, sand, and silica fume admixture. Compressive strength of grout delivered to SWSA6 during grouting operations averaged 1,808 lb/in 2 with a bulk density of 3,549 lb/yd 3

Radioactive waste storage and disposal: the challenge

International Nuclear Information System (INIS)

Prince, A.T.

1978-03-01

Solutions to waste management problems are available. After radium is removed, tailings from uranium ores can be disposed of safely in well-designed retention areas. Work is being done on the processing of non-fuel reactor wastes through incineration, reverse osmosis, and evaporation. Spent fuels have been stored safely for years in pools; dry storage in concrete cannisters is being investigated. Ultimate disposal of high-level wastes will be in deep, stable geologic formations. (LL)

Radioactive waste disposal

International Nuclear Information System (INIS)

Bohm, H.; Closs, K.D.; Kuhn, K.

1981-01-01

The solutions to the technical problem of the disposal of radioactive waste are limited by a) the state of knowledge of reprocessing possibilites, b) public acceptance of the use of those techniques which are known, c) legislative procedures linking licensing of new nuclear power plants to the solution of waste problems, and d) other political constraints. Wastes are generated in the mining and enriching of radioactive elements, and in the operation of nuclear power plants as well as in all fields where radioactive substances may be used. Waste management will depend on the stability and concentration of radioactive materials which must be stored, and a resolution of the tension between numerous small storage sites and a few large ones, which again face problems of public acceptability

The politics of radioactive waste disposal

International Nuclear Information System (INIS)

Kemp, R.

1992-01-01

Plans for radioactive waste disposal have been among the most controversial of all environmental policies, provoking vociferous public opposition in a number of countries. This book looks at the problem from an international perspective, and shows how proposed solutions have to be politically and environmentally, as well as technologically acceptable. In the book the technical and political agenda behind low and intermediate level radioactive waste disposal in the UK, Western Europe, Scandinavia and North America is examined. The technical issues and the industrial proposals and analyses and factors which have been crucial in affecting relative levels of public acceptability are set out. Why Britain has lagged behind countries such as Sweden and France in establishing Low Level Waste (LLW) and Intermediate Level Waste (ILW) sites, the strength of the 'not in my backyard' syndrome in Britain, and comparisons of Britain's decision-making process with the innovative and open pattern followed in the US and Canada are examined. An important insight into the problems facing Nirex, Britain's radioactive waste disposal company, which is seeking to establish an underground waste site at Sellafield in Cumbria is given. (author)

ENTRIA 2014. Memorandum on the disposal of high-level radioactive residuals

International Nuclear Information System (INIS)

Roehlig, Klaus-Juergen; Walther, Clemens; Bach, Friedrich-Wilhelm

2014-01-01

The memorandum on the disposal of high-level radioactive residuals covers the following issues: description of the problem: a ''wicked problem'', risks and NIMBY, the site selection law, international boundary conditions; disposal strategy and types of facilities: safety and reversibility, long-term surface storage, deep storage; risk and safety; procedural justice and the site selection process; social innovations and the requirement of long-term institutions; conclusion - central stress fields.

Deep borehole disposal of plutonium

International Nuclear Information System (INIS)

Gibb, F. G. F.; Taylor, K. J.; Burakov, B. E.

2008-01-01

Excess plutonium not destined for burning as MOX or in Generation IV reactors is both a long-term waste management problem and a security threat. Immobilisation in mineral and ceramic-based waste forms for interim safe storage and eventual disposal is a widely proposed first step. The safest and most secure form of geological disposal for Pu yet suggested is in very deep boreholes and we propose here that the key to successful combination of these immobilisation and disposal concepts is the encapsulation of the waste form in small cylinders of recrystallized granite. The underlying science is discussed and the results of high pressure and temperature experiments on zircon, depleted UO 2 and Ce-doped cubic zirconia enclosed in granitic melts are presented. The outcomes of these experiments demonstrate the viability of the proposed solution and that Pu could be successfully isolated from its environment for many millions of years. (authors)

Mining techniques and some aspects of high-level waste disposal

International Nuclear Information System (INIS)

Hoefnagels, J.A.R.

1980-01-01

The solutions to many problems of underground waste disposal involve mine engineering. This article attempts to highlight chosen issues and thereby create an overall impression, avoiding emphasis on single-aspect calculation. High level waste (H.L.W.) dominates current radioactive waste studies because of its specific characteristics and is therefore dealt with in this paper. However, depending on the method of disposal the other categories of radio active waste might become problems by themselves because of the relatively large quantities involved. (Auth.)

Using the hybrid fuzzy goal programming model and hybrid genetic algorithm to solve a multi-objective location routing problem for infectious waste disposaL

Energy Technology Data Exchange (ETDEWEB)

Wichapa, Narong; Khokhajaikiat, Porntep

2017-07-01

Disposal of infectious waste remains one of the most serious problems in the social and environmental domains of almost every nation. Selection of new suitable locations and finding the optimal set of transport routes to transport infectious waste, namely location routing problem for infectious waste disposal, is one of the major problems in hazardous waste management. Design/methodology/approach: Due to the complexity of this problem, location routing problem for a case study, forty hospitals and three candidate municipalities in sub-Northeastern Thailand, was divided into two phases. The first phase is to choose suitable municipalities using hybrid fuzzy goal programming model which hybridizes the fuzzy analytic hierarchy process and fuzzy goal programming. The second phase is to find the optimal routes for each selected municipality using hybrid genetic algorithm which hybridizes the genetic algorithm and local searches including 2-Opt-move, Insertion-move and ?-interchange-move. Findings: The results indicate that the hybrid fuzzy goal programming model can guide the selection of new suitable municipalities, and the hybrid genetic algorithm can provide the optimal routes for a fleet of vehicles effectively. Originality/value: The novelty of the proposed methodologies, hybrid fuzzy goal programming model, is the simultaneous combination of both intangible and tangible factors in order to choose new suitable locations, and the hybrid genetic algorithm can be used to determine the optimal routes which provide a minimum number of vehicles and minimum transportation cost under the actual situation, efficiently.

Using the hybrid fuzzy goal programming model and hybrid genetic algorithm to solve a multi-objective location routing problem for infectious waste disposaL

International Nuclear Information System (INIS)

Wichapa, Narong; Khokhajaikiat, Porntep

2017-01-01

Disposal of infectious waste remains one of the most serious problems in the social and environmental domains of almost every nation. Selection of new suitable locations and finding the optimal set of transport routes to transport infectious waste, namely location routing problem for infectious waste disposal, is one of the major problems in hazardous waste management. Design/methodology/approach: Due to the complexity of this problem, location routing problem for a case study, forty hospitals and three candidate municipalities in sub-Northeastern Thailand, was divided into two phases. The first phase is to choose suitable municipalities using hybrid fuzzy goal programming model which hybridizes the fuzzy analytic hierarchy process and fuzzy goal programming. The second phase is to find the optimal routes for each selected municipality using hybrid genetic algorithm which hybridizes the genetic algorithm and local searches including 2-Opt-move, Insertion-move and ?-interchange-move. Findings: The results indicate that the hybrid fuzzy goal programming model can guide the selection of new suitable municipalities, and the hybrid genetic algorithm can provide the optimal routes for a fleet of vehicles effectively. Originality/value: The novelty of the proposed methodologies, hybrid fuzzy goal programming model, is the simultaneous combination of both intangible and tangible factors in order to choose new suitable locations, and the hybrid genetic algorithm can be used to determine the optimal routes which provide a minimum number of vehicles and minimum transportation cost under the actual situation, efficiently.

Situation on regulatory aspects of underground disposal of radioactivity wastes in Japan

International Nuclear Information System (INIS)

Murano, T.; Asano, T.; Matsubara, N.

1978-01-01

At present, in Japan, there exists no law specifically regulating the underground disposal of radioactive wastes although various regulations deal with disposal safety measures in a general way. For the moment, apart from the need to gain public acceptance of such disposal, the problem is essentially one of technical feasibility, and a geological study is currently being undertaken by the Science and Technology Agency. This same Agency is also looking at the problem of a long-term waste management system, but it is the Nuclear Safety Commission, created in 1978, which will be primarily responsible for all regulatory aspects of safety. (NEA) [fr

Radioecological activity limits for radioactive waste disposal

International Nuclear Information System (INIS)

Ahmet, E. Osmanlioglu

2006-01-01

Full text: Near surface disposal is an option used by many countries for the disposal of radioactive waste containing mainly short lived radionuclides. Near surface disposal term includes broad range of facilities from simple trenches to concrete vaults. Principally, disposal of radioactive waste requires the implementation of measures that will provide safety for human health and environment now and in the future. For this reason preliminary activity limits should be determined to avoid radioecological problems. Radioactive waste has to be safely disposed in a regulated manner, consistent with internationally agreed principles and standards and with national legislations to avoid serious radioecological problems. The purpose of this study, presents a safety assessment approach to derive operational and post-closure radioecological activity limits for the disposal of radioactive waste. Disposal system has three components; the waste, the facility (incl. engineered barriers) and the site (natural barriers). Form of the waste (unconditioned or conditioned) is effective at the beginning of the migration scenerio. Existence of the engineered barriers in the facility will provide long term isolation of the waste from environment. The site characteristics (geology, groundwater, seismicity, climate etc.) are important for the safety of the system. Occupational exposure of a worker shall be controlled so that the following dose limits are not exceeded: an effective dose of 20mSv/y averaged over 5 consecutive years; and an effective dose of 50mSv in any single year. The effective dose limit for members of the public recommended by ICRP and IAEA is 1 mSv/y for exposures from all man-made sources [1,2]. Dose constraints are typically a fraction of the dose limit and ICRP recommendations (0.3 mSv/y) could be applied [3,4]. Radioecological activity concentration limits of each radionuclide in the waste (Bq/kg) were calculated. As a result of this study radioecological activity

Safely disposing and controlling the various forms of excess military plutonium

International Nuclear Information System (INIS)

Albright, D.

1991-01-01

The growing surplus of plutonium will continue to pose safety, health, and verification problems. Although long term storage and disposal of plutonium seems technically feasible, or at least comparable in technical difficulty to commercial spent fuel disposal, significant political obstacles within the government and the public, may make it difficult to solve this problem. Although options to build verifiable warhead dismantlement facilities or to recycle plutonium in reactors and thus convert separated plutonium into irradiated fuel are straight forward concepts, their realization remains difficult for economic and political reasons. The plutonium recycle option also raises additional proliferation concerns about its impact on civilian nuclear programs. In the absence of a long term solution, the United States can implement various storage or interim disposal options that involve minimal processing, but that ease verification problems and provide adequate safety and protection of public health

Combining computational modelling with radioisotope technology for a more cost- effective and time-efficient method of solving industrial and medical diagnostic problems

International Nuclear Information System (INIS)

Tu, J.Y.; Easey, J.F.; Burch, W.M.

1997-01-01

In this paper, some work on computational modelling for industrial operations and processes will be presented, for example, the modelling of fly-ash flow and the associated prediction of erosion in power utility boilers. The introduction and use of new formulations of encapsulated radioisotopes, currently being research at ANSTO, will open up further possibilities for the utilisation of radiotracer applications for a wider range of validation work not only in industrial but also in medical investigations. Applications of developed models to solving industrial problems will also be discussed in the paper

Important issues in disposal of L/ILW

International Nuclear Information System (INIS)

McCombie, C.

1987-01-01

Today waste disposal is a challenging technical and political issue. In many countries the acceptance of nuclear power has been tied formally or informally to the convincing demonstration that we can dispose of all radioactive wastes with a very high degree of safety exceeding the expected for other toxic or hazardous wastes. The importance of the public acceptance aspects and the more obviously striking characteristics of high-level wastes (HLW) - in particular their high initial radiation, their heat emission and their long decay times - led to an early concentration of effort on planning and analyzing HLW disposal. On the other hand, the problems of disposing of low- and inter-mediate-level wastes (L/ILW) are in many ways more immediate. These wastes are arising today in quantities which can make continued storge troublesome; accordingly increased effort is being expended in many countries on organizing the safe, final disposal of L/ILW. Some of the technical issues of importance which arise in the corresponding planning and analysis of repository projects for L/ILW are discussed in this paper

Argentina: Disposal aspects of RA-1 research reactor decommissioning waste

Energy Technology Data Exchange (ETDEWEB)

Harriague, S; Barberis, C; Cinat, E; Grizutti, C; Scolari, H [Comision Nacional de Energia Atomica, Buenos Aires (Argentina)

2007-12-15

The objective of the project is to analyze disposal aspects of waste from total dismantling of Argentinean research reactors, starting with the oldest one, 48 years old RA-1. In order to estimate decommissioning waste, data was collected from files, area monitoring, measurements, sampling to measure activity and composition, operational history and tracing of operational incidents. Measurements were complemented with neutron activation calculations. Decommissioning waste for RA-1 is estimated to be 71.5 metric tons, most of it concrete (57 tons), the rest being steels, lead and reflector graphite (4.8 tons). Due to their low specific activities, no disposal problems are foreseen in the case of metals and concrete. Disposal of aluminium, steel, lead and concrete is analyzed. On the contrary, as the country has no experience in managing graphite radioactive waste, work was concentrated on that material. Stored (Wigner) energy may exist in RA-1 graphite reflectors irradiated at room temperature. Evaluation of stored energy by calorimetric methods is proposed, and its annealing by inductive heating; HEPA filters should be used to deal with gaseous activity emissions, mainly Cl-36 and C-14. Galvanic corrosion, dust explosion, ignition and oxidation can be addressed and should not become disposal problems. Care must be taken with graphite dust generation and disposal, due to wetting and flotation problems. Lessons learned from the project are presented, and the benefits of sharing international experience are stressed. (author)

Northeast Regional environmental impact study: Waste disposal technical report

Science.gov (United States)

Saguinsin, J. L. S.

1981-04-01

The potential for cumulative and interactive environmental impacts associated with the conversion of multiple generating stations in the Northeast is assessed. The estimated quantities and composition of wastes resulting from coal conversion, including ash and SO2 scrubber sludge, are presented. Regulations governing the use of ash and scrubber sludge are identified. Currently available waste disposal schemes are described. The location, capacity, and projected life of present and potential disposal sites in the region are identified. Waste disposal problems, both hazardous and nonhazardous, are evaluated. Environmental regulations within the region as they pertain to coal conversion and as they affect the choice of conversion alternatives are discussed. A regional waste management strategy for solid waste disposal is developed.

Preliminary study of radioactive waste disposal in granitic underground caves

International Nuclear Information System (INIS)

Carvalho, J.F. de; Carajilescov, P.

1984-01-01

To date, the disposal of radioactive wastes is one of the major problems faced by the nuclear industry. The utilization of granitic underground caves surrounded by a clay envelope is suggested as a safe alternative for such disposal. A preliminary analysis of the dimensions of those deposits is done. (Author) [pt

Deep injection disposal of liquid radioactive waste in Russia

International Nuclear Information System (INIS)

Foley, M.G.; Ballou, L.; Rybal'chenko, A.I.; Pimenov, M.K.; Kostin, P.P.

1998-01-01

Originally published in Russian, Deep Injection Disposal is the most comprehensive account available in the West of the Soviet and Russian practice of disposing of radioactive wastes into deep geological formations. It tells the story of the first 40 years of work in the former Soviet Union to devise, test, and execute a program to dispose by deep injection millions of cubic meters of liquid radioactive wastes from nuclear materials processing. The book explains decisions involving safety aspects, research results, and practical experience gained during the creation and operation of disposal systems. Deep Injection Disposal will be useful for studying other problems worldwide involving the economic use of space beneath the earth's surface. The material in the book is presented with an eye toward other possible applications. Because liquid radioactive wastes are so toxic and the decisions made are so vital, information in this book will be of great interest to those involved in the disposal of nonradioactive waste

The trends of radioactive waste disposal

International Nuclear Information System (INIS)

Nomi, Mitsuhiko

1977-01-01

The disposal of radioactive wastes instead of their treatment has come to be important problem. The future development of nuclear fuel can not be expected unless the final disposal of nuclear fuel cycle is determined. Research and development have been made on the basis of the development project on the treatment of radioactive wastes published by Japan Atomic Energy Commission in 1976. The high level wastes produced by the reprocessing installations for used nuclear fuel are accompanied by strong radioactivity and heat generation. The most promising method for their disposal is to keep them in holes dug at the sea bottom after they are solidified. Middle or low level wastes are divided into two groups; one contains transuranium elements and the other does not. These wastes are preserved on the ground or in shallow strata, while the safe abandonment into the ground or the sea has been discussed about the latter. The co-operations among nations are necessary not only for peaceful utilization of atomic energy but also for radioactive waste disposal. (Kobatake, H.)

Solving the geologic issues in nuclear waste disposal

International Nuclear Information System (INIS)

Towse, D.

1979-01-01

Technical problems with nuclear waste disposal are largely geological. If these are not solved, curtailment of nuclear power development may follow, resulting in loss of an important element in the national energy supply. Present knowledge and credible advances are capable of solving these problems provided a systems view is preserved and a national development plan is followed. This requires identification of the critical controllable elements and a systematic underground test program to prove those critical elements. Waste migration can be understood and controlled by considering the key elements in the system: the system geometry, the hydrology, and the waste-rock-water chemistry. The waste program should: (1) identify and attack the critical problems first; (2) provide tests and demonstration at real disposal sites; and (3) schedule elements with long lead-times for early start and timely completion

On the disposal of solid radioactive wastes at hospitals

International Nuclear Information System (INIS)

Rogge, B.; Lewe, P.

1987-01-01

The disposal of radioactive materials in hospitals represents a considerable problem from the point of view of economics and organisation as well as from the point of view of radiological safety. On the one-hand, groups of people (nursing personal and clean-up crews) are involved in the handling of contaminated materials who can be instructed in special handling procedures only to a limited degree with the result that simple and clear procedures must be developed; on the other hand, such simply structured routes of disposal result in enormous volumes of radioactive waste, which represent a considerable cost factor. At the Offenbach City Hospital a concept has been created which takes these problems into account. It consists of nuclide-specific collection in groups, reduction of volume by breaking up of materials, interim storage, and government approved disposal as special hospital waste materials. (orig.) [de

Erosion of surface and near surface disposal facilities

International Nuclear Information System (INIS)

1988-06-01

A literature search was undertaken to identify existing data and analytical procedures regarding the processes of gully erosion. The applicability of the available information to the problems of gully erosion potential at surface and near surface disposal sites is evaluated. It is concluded that the existing knowledge regarding gully erosion is insufficient to develop procedures to ensure the long-term stability of disposal sites. Recommendations for further research are presented. 46 refs

Nuclear waste disposal: Can there be a resolution? Past problems and future solutions

Energy Technology Data Exchange (ETDEWEB)

Ahearne, J [Scientific Research Society, Sigma Xi, Research Triangle Park, NC (United States)

1990-07-01

Why does the high level waste problem have to be solved now? There are perhaps three answers to that question. First, to have a recovery of nuclear power. But a lack of resolution of the high level waste problem is not the principal reason that nuclear power has foundered and, consequently, solving it will not automatically revive nuclear power. However, if the nuclear industry is adamantly convinced that this is the key to reviving nuclear power, then the nuclear industry should demonstrate its conviction by putting much greater effort into resolving the high level waste problem technically, not through public relations. For example, a substantial effort on the actinide burning approach might demonstrate, in the old American phrase, 'putting your money where your mouth is'. Second, the high level waste problem must be solved now because it is a devil's brew. However, chemical wastes last longer, as we all know, than do the radioactive wastes. As one expert has noted: 'There is real risk in nuclear power, just as there is real risk in coal power.... For some of [these risks], like the greenhouse effect, the potential damage is devastating. While for others, like nuclear accidents, the risk is limited, but imaginations are not. For still others, like the risk posed by a high-level waste repository, there is essentially nothing outside the imagination of the gullible.' Furthermore, any technical solution or any solution to a risky problem requires one to think carefully. It is often better to do it right than quickly. A third reason for requiring it to be solved right now is that HLW disposal is a major technical problem blocking a potentially valuable energy source. But we need a new solution. The current solutions are not working. I believe that we ought to recognize the failure of the geologic repository approach. I believe the federal government should identify, with industry's assistance, the best techniques for surface storage. Some federal locations should be

Nuclear waste disposal: Can there be a resolution? Past problems and future solutions

International Nuclear Information System (INIS)

Ahearne, J.

1990-01-01

Why does the high level waste problem have to be solved now? There are perhaps three answers to that question. First, to have a recovery of nuclear power. But a lack of resolution of the high level waste problem is not the principal reason that nuclear power has foundered and, consequently, solving it will not automatically revive nuclear power. However, if the nuclear industry is adamantly convinced that this is the key to reviving nuclear power, then the nuclear industry should demonstrate its conviction by putting much greater effort into resolving the high level waste problem technically, not through public relations. For example, a substantial effort on the actinide burning approach might demonstrate, in the old American phrase, 'putting your money where your mouth is'. Second, the high level waste problem must be solved now because it is a devil's brew. However, chemical wastes last longer, as we all know, than do the radioactive wastes. As one expert has noted: 'There is real risk in nuclear power, just as there is real risk in coal power.... For some of [these risks], like the greenhouse effect, the potential damage is devastating. While for others, like nuclear accidents, the risk is limited, but imaginations are not. For still others, like the risk posed by a high-level waste repository, there is essentially nothing outside the imagination of the gullible.' Furthermore, any technical solution or any solution to a risky problem requires one to think carefully. It is often better to do it right than quickly. A third reason for requiring it to be solved right now is that HLW disposal is a major technical problem blocking a potentially valuable energy source. But we need a new solution. The current solutions are not working. I believe that we ought to recognize the failure of the geologic repository approach. I believe the federal government should identify, with industry's assistance, the best techniques for surface storage. Some federal locations should be

Derivation of activity limits for the disposal of radioactive waste in near surface disposal facilities

International Nuclear Information System (INIS)

2003-12-01

Radioactive waste must be managed safely, consistent with internationally agreed safety standards. The disposal method chosen for the waste should be commensurate with the hazard and longevity of the waste. Near surface disposal is an option used by many countries for the disposal of radioactive waste containing mainly short lived radionuclides and low concentrations of long lived radionuclides. The term 'near surface disposal' encompasses a wide range of design options, including disposal in engineered structures at or just below ground level, disposal in simple earthen trenches a few metres deep, disposal in engineered concrete vaults, and disposal in rock caverns several tens of metres below the surface. The use of a near surface disposal option requires design and operational measures to provide for the protection of human health and the environment, both during operation of the disposal facility and following its closure. To ensure the safety of both workers and the public (both in the short term and the long term), the operator is required to design a comprehensive waste management system for the safe operation and closure of a near surface disposal facility. Part of such a system is to establish criteria for accepting waste for disposal at the facility. The purpose of the criteria is to limit the consequences of events which could lead to radiation exposures and in addition, to prevent or limit hazards, which could arise from non-radiological causes. Waste acceptance criteria include limits on radionuclide content concentration in waste materials, and radionuclide amounts in packages and in the repository as a whole. They also include limits on quantity of free liquids, requirements for exclusion of chelating agents and pyrophoric materials, and specifications of the characteristics of the waste containers. Largely as a result of problems encountered at some disposal facilities operated in the past, in 1985 the IAEA published guidance on generic acceptance

OPTIMAL ALLOCATION OF LANDFILL DISPOSAL SITE: A FUZZY MULTI-CRITERIA APPROACH

Directory of Open Access Journals (Sweden)

Ajit P. Singh, A. K. Vidyarthi

2008-01-01

Full Text Available The arbitrary disposal through land-fill sites and also the unscientific management of solid wastes generated by domestic, commercial and industrial activities leading to serious problems of health, sanitation and environmental degradation in India demand an immediate proper solid waste disposal planning otherwise it may cause a serious problem, especially in small and medium-sized cities/towns if proper steps are not initiated now. The present paper aims to develop decision support systems to allocate the best landfill disposal site among the given alternative sites for Vidya Vihar, Pilani, Rajasthan, India. The technique is applied to determine the overall strategy for planning of solid waste disposal and management, while taking into account its environmental impact, as well as economical, technical and sustainable development issues. The model effectively reflects dynamic, interactive, and uncertain characteristics of the solid waste management system and provides decision-makers with a decision tool to make a better decision while choosing a municipal solid waste management strategy.

Fluorescent lamp and ballast disposal-efficiency and the environment: Panel discussion

Energy Technology Data Exchange (ETDEWEB)

Bleasby, P.

1996-01-01

This panel discussion looked at the present state of problems related to the disposal of fluorescent lamps and ballasts. EPA has not issued a ruling defining what is to be done, and as a result different areas of the country, and different users are treating the products differently. The authors review the history of the problem, where the environmental concerns are, possible alternatives for disposal, be it landfill, recycling, incineration, or treatment as hazardous wastes, and policy concerns with regard to this issue.

Advances in poultry litter disposal technology--a review.

Science.gov (United States)

Kelleher, B P; Leahy, J J; Henihan, A M; O'Dwyer, T F; Sutton, D; Leahy, M J

2002-05-01

The land disposal of waste from the poultry industry and subsequent environmental implications has stimulated interest into cleaner and more useful disposal options. The review presented here details advances in the three main alternative disposal routes for poultry litter, specifically in the last decade. Results of experimental investigations into the optimisation of composting, anaerobic digestion and direct combustion are summarised. These technologies open up increased opportunities to market the energy and nutrients in poultry litter to agricultural and non-agricultural uses. Common problems experienced by the current technologies are the existence and fate of nitrogen as ammonia, pH and temperature levels, moisture content and the economics of alternative disposal methods. Further advancement of these technologies is currently receiving increased interest, both academically and commercially. However, significant financial incentives are required to attract the agricultural industry.

Modeling of release of radionuclides from an engineered disposal facility for shallow-land disposal of low-level radioactive wastes

International Nuclear Information System (INIS)

Matsuzuru, H.; Suzuki, A.

1989-01-01

The computer code, ENBAR-1, for the simulation of radionuclide releases from an engineered disposal facility has been developed to evaluate the source term for subsequent migration of radionuclides in and through a natural barrier. The system considered here is that a waste package (waste form and container) is placed, together with backfill materials, into a concrete pit as a disposal unit for shallow-land disposal of low-level radioactive wastes. The code developed includes the following modules: water penetration into a concrete pit, corrosion of a drum as a container, leaching of radionuclides from a waste form, migration of radionuclides in backfill materials, release of radionuclides from the pit. The code has the advantage of its simplicity of operation and presentation while still allowing comprehensive evaluation of each element of an engineered disposal facility to be treated. The performance and source term of the facility might be readily estimated with a few key parameters to define the problem

Final disposal of nuclear waste

Energy Technology Data Exchange (ETDEWEB)

Anon,

1995-10-01

The nuclear industry argues that high level radioactive waste can be safely disposed of in deep underground repositories. As yet, however, no such repositories are in use and the amount of spent nuclear fuel in ponds and dry storage is steadily increasing. Although the nuclear industry further argues that storage is a safe option for up to 50 years and has the merit of allowing the radioactivity of the fuel to decay to a more manageable level, the situation seems to be far from ideal. The real reasons for procrastination over deep disposal seem to have as much to do with politics as safe technology. The progress of different countries in finding a solution to the final disposal of high level waste is examined. In some, notably the countries of the former Soviet Union, cost is a barrier; in others, the problem has not yet been faced. In these countries undertaking serious research into deep disposal there has been a tendency, in the face of opposition from environmental groups, to retreat to sites close to existing nuclear installations and to set up rock laboratories to characterize them. These sites are not necessarily the best geologically, but the laboratories may end up being converted into actual repositories because of the considerable financial investment they represent. (UK).

Final disposal of nuclear waste

International Nuclear Information System (INIS)

Anon.

1995-01-01

The nuclear industry argues that high level radioactive waste can be safely disposed of in deep underground repositories. As yet, however, no such repositories are in use and the amount of spent nuclear fuel in ponds and dry storage is steadily increasing. Although the nuclear industry further argues that storage is a safe option for up to 50 years and has the merit of allowing the radioactivity of the fuel to decay to a more manageable level, the situation seems to be far from ideal. The real reasons for procrastination over deep disposal seem to have as much to do with politics as safe technology. The progress of different countries in finding a solution to the final disposal of high level waste is examined. In some, notably the countries of the former Soviet Union, cost is a barrier; in others, the problem has not yet been faced. In these countries undertaking serious research into deep disposal there has been a tendency, in the face of opposition from environmental groups, to retreat to sites close to existing nuclear installations and to set up rock laboratories to characterize them. These sites are not necessarily the best geologically, but the laboratories may end up being converted into actual repositories because of the considerable financial investment they represent. (UK)

Hazardous Waste Development, Demonstration, and Disposal (HAZWDDD) Program Plan

International Nuclear Information System (INIS)

McGinnis, C.P.; Eisenhower, B.M.; Reeves, M.E.; DePaoli, S.M.; Stinton, L.H.; Harrington, E.H.

1989-02-01

The objective of the Hazardous Waste Development, Demonstration and Disposal (HAZWDDD) Program Plan is to ensure that the needs for treatment and disposal of all its hazardous and mixed wastes have been identified and planned for. A multifaceted approach to developing and implementing this plan is given, including complete plans for each of the five installations, and an overall integrated plan is also described in this report. The HAZWDDD Plan accomplishes the following: (1) provides background and organizational information; (2) summarizes the 402 hazardous and mixed waste streams from the five installations by grouping them into 13 general waste categories; (3) presents current treatment, storage, and disposal capabilities within Energy Systems; (4) develops a management strategy by outlining critical issues, presents flow sheets describing management schemes for problem waste streams, and builds on the needs identified; (5) outlines specific activities needed to implement the strategy developed; and (6) presents schedule and budget requirements for the next decade. The HAZWDDD Program addresses current and future technical problems and regulatory issues and uncertainties. Because of the nature and magnitude of the problems in hazardous and mixed waste management, substantial funding will be required. 10 refs., 39 figs., 16 tabs

Post-disposal safety assessment of toxic and radioactive waste: waste types, disposal practices, disposal criteria, assessment methods and post-disposal impacts

International Nuclear Information System (INIS)

Torres, C.; Simon, I.; Little, R.H.; Charles, D.; Grogan, H.A.; Smith, G.M.; Sumerling, T.J.; Watkins, B.M.

1993-01-01

The need for safety assessments of waste disposal stems not only from the implementation of regulations requiring the assessment of environmental effects, but also from the more general need to justify decisions on protection requirements. As waste-disposal methods have become more technologically based, through the application of more highly engineered design concepts and through more rigorous and specific limitations on the types and quantities of the waste disposed, it follows that assessment procedures also must become more sophisticated. It is the overall aim of this study to improve the predictive modelling capacity for post-disposal safety assessments of land-based disposal facilities through the development and testing of a comprehensive, yet practicable, assessment framework. This report records all the work which has been undertaken during Phase 1 of the study. Waste types, disposal practices, disposal criteria and assessment methods for both toxic and radioactive waste are reviewed with the purpose of identifying those features relevant to assessment methodology development. Difference and similarities in waste types, disposal practices, criteria and assessment methods between countries, and between toxic and radioactive wastes are highlighted and discussed. Finally, an approach to identify post-disposal impacts, how they arise and their effects on humans and the environment is described

Modularized system for disposal of low-level radioactive waste

International Nuclear Information System (INIS)

Mallory, C.W.; DiSibio, R.

1985-01-01

A modularized system for the disposal of low-level radioactive waste is presented that attempts to overcome the past problems with shallow land burial and gain public acceptance. All waste received at the disposal site is packaged into reinforced concrete modules which are filled with grout, covered and sealed. The hexagonal shape modules are placed in a closely packed array in a disposal unit. The structural stability provided by the modules allow a protective cover constructed of natural materials to be installed, and the disposal units are decommissioned as they are filled. The modules are designed to be recoverable in the event remedial action is necessary. The cost of disposal with a facility of this type is comparable to current prices of shallow land burial facilities. The system is intended to address the needs of generators, regulators, communities, elected officials, licensees and future generations

Nuclear waste disposal

International Nuclear Information System (INIS)

Hare, Tony.

1990-01-01

The Save Our Earth series has been designed to appeal to the inquiring minds of ''planet-friendly'' young readers. There is now a greater awareness of environmental issues and an increasing concern for a world no longer able to tolerate the onslaught of pollution, the depletion of natural resources and the effects of toxic chemicals. Each book approaches a specific topic in a way that is exciting and thought-provoking, presenting the facts in a style that is concise and appropriate. The series aims to demonstrate how various environmental subjects relate to our lives, and encourages the reader to accept not only responsibility for the planet, but also for its rescue and restoration. This volume, on nuclear waste disposal, explains how nuclear energy is harnessed in a nuclear reactor, what radioactive waste is, what radioactivity is and its effects, and the problems and possible solutions of disposing of nuclear waste. An awareness of the dangers of nuclear waste is sought. (author)

Nuclear waste disposal. A wicked and highly conflict bearing societal problem; Nukleare Entsorgung. Ein ''wicked'' und hoechst konfliktbehaftetes Gesellschaftsproblem

Energy Technology Data Exchange (ETDEWEB)

Brunnengraeber, Achim; Mez, Lutz [Freie Univ. Berlin (Germany). Forschungszentrum fuer Umweltpolitik; Di Nucci, Maria Rosaria; Schreuers, Miranda [Freie Univ. Berlin (Germany)

2012-12-15

The final disposal of nuclear wastes is called ''messy'' or ''wicked'' in the political science literature. The highly complicated problems are characterized by a number of features such as intra- and inter-generational aspects and ethical questions. In the case of stakeholders the differences concern ideologies, interests, merits and preferences that cause conflicts. The search for solutions is complicated due to interacting political, social, ecologic, economic and technical aspects. The concepts ''wicked problems'' and ''multi-level-governance'' are promising approaches to solve the complicated situation.

Investigating the construction of open-quotes pyramidclose quotes super-structures to dispose of radioactive and hazardous waste

International Nuclear Information System (INIS)

Miller, D.J.

1994-01-01

The technical challenges involved in disposing of radioactive and hazardous waste using systems that rely on open-quotes natural barriersclose quotes have been underestimated. Technology has advanced dramatically in the areas of materials, science, and engineering. As a result, traditional approaches to waste disposal must be rethought, focusing instead on ways to apply new technology breakthroughs to waste disposal problems. This paper will discuss problems currently faced by waste disposal systems that rely on natural barriers for containment, propose a general design and approach for constructing pyramid super-structures to dispose of (and store) waste, and present the benefits of such a system. The originality of this paper is that it proposes the construction of fully retrievable waste disposal systems that capitalize on the unique geometric properties of a pyramid and rely on engineered barriers and preventive measurements for containment, rather than natural barriers. In addition, this paper offers a new perspective on waste disposal issues confronting many countries. The desired effect is that by challenging conventional thought, new ideas could be developed to help solve existing problems. This paper is of specific interest to: (1) Policy makers, decisionmakers, and managers because the paper discusses the root causes of problems facing waste disposal and possible solutions. (2) Regulators because the paper discusses reasons for relying more on engineered barriers and preventive measurements to achieve confidence and reliability in containment. (3) Design engineers the paper offers new concepts for engineered barriers. 21 refs., 2 figs., 2 tabs

Fire analyses in central and disposal tunnels by APROS

International Nuclear Information System (INIS)

Peltokorpi, L.; Kukkola, T.; Nieminen, J.

2012-12-01

The central tunnels and the disposal tunnels on the north-east disposal area are the target areas of the fire studies. Target is to maintain under pressure in the fire zone in case of a fire. In the central tunnels a fire of a drilling jumbo with moderate fire propagation is used as heat release rate. In the disposal tunnel the heat release rate of a canister transfer and installation vehicle fire received as a result of the pyrolysis analyze as well as an average heat release rate of a van fire are used. Inlet air is to be conducted to the back end of the fire zone and the exhaust is to be lead out from the beginning of the fire zone. The worst location of the fire is in the beginning of the fire zone just below of the exhaust air clap valve. The size of the fire zone does not have big impact on pressure. In all analyzed cases the fire zone remains too long time over pressurized. Inlet air flow of a 30 m 3 /s is too much. The rotation controlled booster blowers will solve the pressure problems of the fire zone in fire cases. The rotation is controlled by the fire zone pressure. The fire of the canister transfer and installation vehicle in the central tunnel will not cause problems. The disposal tunnel fire door should be kept open, if the canister transfer and installation vehicle or the bentonite blocks transfer and installation vehicle is driven into the disposal tunnel. If a fire is caught in the disposal tunnel then the fire zone in the central tunnel is to be closed and the pressure is controlled by the rotation controlled booster blowers. If a personnel car or a van is driven into the disposal tunnel, then fire door of the disposal is to be kept closed against fires in the central tunnel. (orig.)

Use of abandoned coal/lignite open pits for waste disposal in selected European countries

International Nuclear Information System (INIS)

Libicki, J.S.

1989-01-01

The use of abandoned coal/lignite pits as disposal sites for solid waste appears to be a reasonable approach to a difficult problem, especially if they are located close to the waste source. However, a potential for groundwater and soil pollution exists. This issue was discussed by a Group of Experts on Opencast Mining of the UN Economic Commission for Europe because most of the sites are operated by mining companies. This paper contains the major topics of discussion including the significance of the problem, legal aspects, characteristics of the open pits, waste intended for disposal, investigations required to obtain a disposal permit, disposal techniques, protection measures, monitoring environmental impacts, and research trends. A few countries are used as examples

Defence nuclear waste disposal in Russia. International perspective

International Nuclear Information System (INIS)

Stenhouse, M.J.; Kirko, V.I.

1998-01-01

Significant amounts of liquid and solid radioactive waste have been generated in Russia during the production of nuclear weapons, and there is an urgent need to find suitable ways to manage these wastes in a way that protects both the current population and future generations. This book contains contributions from pure and applied scientists and other representatives from Europe, North America, and Russia, who are, or have been, actively involved in the field of radioactive waste management and disposal. First-hand experience of specific problems associated with defence-related wastes in the USA and the Russian Federation is presented, and current plans are described for the disposal of solid wastes arising from civilian nuclear power production programmes in other countries, including Belgium, Bulgaria, Canada, Germany and the UK. The book provides a good insight into ongoing research at local and national level within Russia, devoted to the safe disposal of defence-related radioactive waste. It also demonstrates how existing expertise and technology from civilian nuclear waste management programmes can be applied to solving the problems created by nuclear defence programmes. Contributions address methods of immobilisation, site selection methodology, site characterisation techniques and data interpretation, the key elements of safety/performance assessments of planned deep (geological) repositories for radioactive waste, and radionuclide transport modelling. Concerns associated with certain specific nuclear waste disposal concepts and repository sites are also presented. refs

Nuclear waste disposal: two social criteria

International Nuclear Information System (INIS)

Rochlin, G.I.

1977-01-01

Two criteria--technical irreversibility and site multiplicity--have been suggested for use in establishing standards for the disposal of nuclear wastes. They have been constructed specifically to address the reduction of future risk in the face of inherent uncertainty concerning the social and political developments that might occur over the required periods of waste isolation, to provide for safe disposal without the requirement of a guaranteed future ability to recognize, detect, or repair errors and failures. Decisions as to how to apply or weigh these criteria in conjunction with other waste management goals must be made by societies and their governments. The purpose of this paper was not to preempt this process, but to construct a framework that facilitates consideration of the ethical and normative components of the problem of nuclear waste disposal. The minimum ethical obligation of a waste disposal plan is to examine most thoroughly the potential consequences of present actions, to acknowledge them openly, and to minimize the potential for irremediable harm. An ethically sound waste management policy must reflect not only our knowledge and skills, but our limitations as well

The view of the geotechnical engineering on the radioactive waste disposal

International Nuclear Information System (INIS)

Komada, Hiroya

2004-01-01

The state of radioactive waste disposal produced by the nuclear fuel cycle facilities and the future problems of geotechnical engineering are stated. Concept of classification of radioactive waste and their disposal, the present state of operating waste and TRU waste in the low level radioactive waste and the high level radioactive waste are explained. On the future problems, evaluation of ground water flow, long period estimation of natural phenomena, mixed earth with bentonite as a buffer and cement materials are discussed. The geological disposal of radioactive waste, which kept them at more than 200 m underground, has two important different points from the general geotechnical engineering such as a system covered inhomogeneous large space of natural geological features and very long time (some million year) considered. (S.Y.)

DSEM, Radioactive Waste Disposal Site Economic Model

International Nuclear Information System (INIS)

Smith, P.R.

2005-01-01

1 - Description of program or function: The Disposal Site Economic Model calculates the average generator price, or average price per cubic foot charged by a disposal facility to a waste generator, one measure of comparing the economic attractiveness of different waste disposal site and disposal technology combinations. The generator price is calculated to recover all costs necessary to develop, construct, operate, close, and care for a site through the end of the institutional care period and to provide the necessary financial returns to the site developer and lender (when used). Six alternative disposal technologies, based on either private or public financing, can be considered - shallow land disposal, intermediate depth disposal, above or below ground vaults, modular concrete canister disposal, and earth mounded concrete bunkers - based on either private or public development. 2 - Method of solution: The economic models incorporate default cost data from the Conceptual Design Report (DOE/LLW-60T, June 1987), a study by Rodgers Associates Engineering Corporation. Because all costs are in constant 1986 dollars, the figures must be modified to account for inflation. Interest during construction is either capitalized for the private developer or rolled into the loan for the public developer. All capital costs during construction are depreciated over the operation life of the site using straight-line depreciation for the private sector. 3 - Restrictions on the complexity of the problem: Maxima of - 100 years post-operating period, 30 years operating period, 15 years pre-operating period. The model should be used with caution outside the range of 1.8 to 10.5 million cubic feet of total volume. Depreciation is not recognized with public development

Radioactive waste disposal : policies and practices in New Zealand

International Nuclear Information System (INIS)

Robertson, M.K.

1996-01-01

The management of radioactive waste and its ultimate dispoal have been a significant problem for the nuclear industry. A lot of resources have been devoted to developing management and dispoal systems. As well as being one of the major technical problems, it has been a very significant public relations issue. Public concern about risks associated with disposal of radioactive waste has been on a global scle. It has focused on local issues in some countries, but generl attitudes have been common worldwide. Great differences exist between countries in the scale and aspects of nuclear technoloy in use. In particular the presence or absence of a nuclear power programme, and to a lesser extent of any nuclear reactors, greatly influence the magnitude of the waste disposal problem. Nevertheless, public perceptions of the problem are to some degree independent of these differences. What radioactive wastes are there in New Zealand? Is there a hazard to the New Zealand public or the New Zealand environment from current radioactive waste disposal practices? What policies are in place to control these practices? This report seeks to provide some information on these questions. It also brings together in one document the waste disposal policies followed by the National Radiation Laboratory for different uses of radioactive mateials. Except for some small quantities which are exempt from most controls, radioactive material can be used in New Zealand only under the control of a person holding a licence under the Radiation Protection Act 1965. All requirements of the Radiation Protection Regulations 1982 must also be observed. More detailed safety advice and further mandatory requirements are contained in codes of safe practice. Compliance with one of these is a condition on most licencees. These provisions are administered by the National Radiation Laboratory (NRL) of the Ministry of Health. (author). 7 refs., 2 tabs., 1 fig

Cost calculation and financial measures for high-level waste disposal business

International Nuclear Information System (INIS)

Sekiguchi, Hiromasa.

1987-01-01

A study is made on the costs for disposal of high-level wastes, centering on financial problems involving cost calculation for disposal business and methods and systems for funding the business. The first half of the report is focused on calculation of costs for disposal business. Basic equations are shown to calculate the total costs required for a disposal plant and the costs for disposal of one unit of high-level wastes. A model is proposed to calculate the charges to be paid by electric power companies to the plant for disposal of their wastes. Another equation is derived to calculate the disposal charge per kWh of power generation in a power plant. The second half of the report is focused on financial measures concerning expenses for disposal. A financial basis should be established for the implementation of high-level waste disposal. It is insisted that a reasonable method for estimating the disposal costs should be set up and it should be decided who will pay the expenses. Discussions are made on some methods and systems for funding the disposal business. An additional charge should be included in the electricity bill to be paid by electric power users, or it should be included in tax. (Nogami, K.)

Social and economic aspects of radioactive waste disposal: considerations for institutional management

International Nuclear Information System (INIS)

Carter, L.J.

1985-01-01

The problem of nuclear waste disposal has always been recognized as one that is as much political as it is technical. This could explain why the National Academy of Science is just now showing interest in the social and economic aspects of nuclear waste disposal. It has just now issued a report called Social Aspects of Radioactive Waste Disposal: Considerations for Industrial Management. This article is a critical review of the content of this report

Accounting for socio-economic effects in nuclear waste disposal projects

International Nuclear Information System (INIS)

Van Hove, E.

1996-01-01

The disposal of nuclear waste has become highly controversial. This paper presents the approach taken by NIRAS, the Belgian agency for the disposal of nuclear waste, to come to a decision on the establishment of a site for the permanent disposal of low level nuclear waste. A formal model is elaborated to take social effects of such a project into account, allowing for a balanced discussion of positive and negative effects at the local level. It is too early to tell it the model described in detail in this paper con solve the problems encountered by disposal agencies. The approach discussed, does however, respond to need experienced on a international scale. The paper emphasises the need for openness in the fact of assertive and articulate citizens who no longer accept the paternalistic approach. The public must not feel that there is any lack of clarity about waste projects or they will quickly voice their opinions and any opposition they feel. As far as siting is concerned, most of the controversies are fuelled ba a basic notion of 'unfairness'. Somehow the burdens seem to be imposed on parties other than those who reap the benefits. An approach to decision making through local negotiation on all aspects of a disposal projects should allow the problem of fairness to be treated in a more constructive way. (author)

Saltstone processing startup at the Savannah River Plant

International Nuclear Information System (INIS)

Wilhite, E.L.; Langton, C.A.; Sturm, H.F.; Hooker, R.L.; Occhipinti, E.S.

1988-01-01

High-level nuclear wastes are stored in large underground tanks at the Savannah River Plant. Processing of this waste in preparation for ultimate disposal will begin in 1988. The waste will be processed to separate the high-level radioactive fraction from the low-level radioactive fraction. The separation will be made in existing waste tanks by a process combining precipitation, adsorption, and filtration. The high-level fraction will be vitrified into borosilicate glass in the Defense Waste Processing Facility (DWPF) for permanent disposal in a federal repository. The low-level fraction (decontaminated salt solution) will be mixed with a cementitious slag-flyash blend. The resulting wasteform, saltstone, will be disposed of onsite by emplacement in an engineered facility. Waste properties, disposal facility details, and wasteform characteristics are discussed. In particular, details of saltstone processing, focusing on experience obtained from facility startup, are presented

10 CFR 61.52 - Land disposal facility operation and disposal site closure.

Science.gov (United States)

2010-01-01

... DISPOSAL OF RADIOACTIVE WASTE Technical Requirements for Land Disposal Facilities § 61.52 Land disposal... wastes by placing in disposal units which are sufficiently separated from disposal units for the other... between any buried waste and the disposal site boundary and beneath the disposed waste. The buffer zone...

Preliminary disposal limits, plume interaction factors, and final disposal limits

Energy Technology Data Exchange (ETDEWEB)

Flach, G. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2018-01-11

In the 2008 E-Area Performance Assessment (PA), each final disposal limit was constructed as the product of a preliminary disposal limit and a plume interaction factor. The following mathematical development demonstrates that performance objectives are generally expected to be satisfied with high confidence under practical PA scenarios using this method. However, radionuclides that experience significant decay between a disposal unit and the 100-meter boundary, such as H-3 and Sr-90, can challenge performance objectives, depending on the disposed-of waste composition, facility geometry, and the significance of the plume interaction factor. Pros and cons of analyzing single disposal units or multiple disposal units as a group in the preliminary disposal limits analysis are also identified.

Who regulates the disposal of low-level radioactive waste under the Low-Level Radioactive Waste Policy Act

International Nuclear Information System (INIS)

Mostaghel, D.M.

1988-01-01

The present existence of immense quantities of low-level nuclear waste, a federal law providing for state or regional control of such waste disposal, and a number of state disposal laws challenged on a variety of constitutional grounds underscore what currently may be the most serious problem in nuclear waste disposal: who is to regulate the disposal of low-level nuclear wastes. This problem's origin may be traced to crucial omissions in the Atomic Energy Act of 1946 and its 1954 amendments (AEA) that concern radioactive waste disposal. Although the AEA states that nuclear materials and facilities are affected with the public interest and should be regulated to provide for the public health and safety, the statute fails to prescribe specific guidelines for any nuclear waste disposal. The Low-Level Radioactive Waste Policy Act of 1980 (LLRWPA) grants states some control over radioactive waste disposal, an area from which they were previously excluded by the doctrine of federal preemption. This Comment discusses the question of who regulates low-level radioactive waste disposal facilities by examining the following: the constitutional doctrines safeguarding federal government authority; area of state authority; grants of specific authority delegations under the LLRWPA and its amendment; and finally, potential problems that may arise depending on whether ultimate regulatory authority is deemed to rest with single states, regional compacts, or the federal government

Deep Borehole Disposal as an Alternative Concept to Deep Geological Disposal

Energy Technology Data Exchange (ETDEWEB)

Lee, Jongyoul; Lee, Minsoo; Choi, Heuijoo; Kim, Kyungsu [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2016-10-15

In this paper, the general concept and key technologies for deep borehole disposal of spent fuels or HLW, as an alternative method to the mined geological disposal method, were reviewed. After then an analysis on the distance between boreholes for the disposal of HLW was carried out. Based on the results, a disposal area were calculated approximately and compared with that of mined geological disposal. These results will be used as an input for the analyses of applicability for DBD in Korea. The disposal safety of this system has been demonstrated with underground research laboratory and some advanced countries such as Finland and Sweden are implementing their disposal project on commercial stage. However, if the spent fuels or the high-level radioactive wastes can be disposed of in the depth of 3-5 km and more stable rock formation, it has several advantages. Therefore, as an alternative disposal concept to the mined deep geological disposal concept (DGD), very deep borehole disposal (DBD) technology is under consideration in number of countries in terms of its outstanding safety and cost effectiveness. In this paper, the general concept of deep borehole disposal for spent fuels or high level radioactive wastes was reviewed. And the key technologies, such as drilling technology of large diameter borehole, packaging and emplacement technology, sealing technology and performance/safety analyses technologies, and their challenges in development of deep borehole disposal system were analyzed. Also, very preliminary deep borehole disposal concept including disposal canister concept was developed according to the nuclear environment in Korea.

Deep Borehole Disposal as an Alternative Concept to Deep Geological Disposal

International Nuclear Information System (INIS)

Lee, Jongyoul; Lee, Minsoo; Choi, Heuijoo; Kim, Kyungsu

2016-01-01

In this paper, the general concept and key technologies for deep borehole disposal of spent fuels or HLW, as an alternative method to the mined geological disposal method, were reviewed. After then an analysis on the distance between boreholes for the disposal of HLW was carried out. Based on the results, a disposal area were calculated approximately and compared with that of mined geological disposal. These results will be used as an input for the analyses of applicability for DBD in Korea. The disposal safety of this system has been demonstrated with underground research laboratory and some advanced countries such as Finland and Sweden are implementing their disposal project on commercial stage. However, if the spent fuels or the high-level radioactive wastes can be disposed of in the depth of 3-5 km and more stable rock formation, it has several advantages. Therefore, as an alternative disposal concept to the mined deep geological disposal concept (DGD), very deep borehole disposal (DBD) technology is under consideration in number of countries in terms of its outstanding safety and cost effectiveness. In this paper, the general concept of deep borehole disposal for spent fuels or high level radioactive wastes was reviewed. And the key technologies, such as drilling technology of large diameter borehole, packaging and emplacement technology, sealing technology and performance/safety analyses technologies, and their challenges in development of deep borehole disposal system were analyzed. Also, very preliminary deep borehole disposal concept including disposal canister concept was developed according to the nuclear environment in Korea

Radioactive waste disposal: an international law perspective

International Nuclear Information System (INIS)

Barrie, G.N.

1989-01-01

The question of radioactive waste disposal is the most intractable technical and political problem facing nuclear industry. Environmentalists world-wide demand a nuclear waste policy that must be ecologically acceptable internationally. Radioactive wastes and oil pollution were the first two types of marine pollution to receive international attention and various marine pollution controls were established. Ocean disposal was co-ordinated by the Nuclear Energy Agency and the Organization of Economic Co-operation and Development in 1967. The first treaty was the 1958 Convention on the High Seas (High Seas Convention). In response to its call for national co-operation the International Atomic Energy Agency (IAEA) established its Brynielson panel. The IAEA first issued guidelines on sea dumping in 1961. The London Dumping Convention, written in 1972, is the only global agreement concerned solely with the disposal of wastes in the marine environment by dumping. None of the global agreements make specific reference to sea-bed disposal of high-level radioactive wastes. Negotiations began at the Third UN Conference on the Law of the Sea (UNCLOS III) for the codification of a comprehensive treaty concerned with the protection, conservation, sustainable use and development of the marine environment. Burial in deep geological formations is a method of HLW disposal which decreases the chances of accidental intrusion by mankind and has little likelihood of malicious intrusion. National waste management programmes of different countries differ but there is agreement on the acceptable technical solutions to issues of waste management. The final disposition of HLW - storage or disposal - has not been decisively determined, but there is growing consensus that geological land-based disposal is the most viable alternative. Expanded international technical co-operation could well reduce the time needed to develop effective waste disposal mechanisms

Radioactive wastes: a world problem. Les dechets nucleaires: un probleme mondial

Energy Technology Data Exchange (ETDEWEB)

Schapira, J P [Centre National de la Recherche Scientifique (CNRS), 75 - Paris (FR)

1991-02-01

In all countries endowed with nuclear program, radioactive wastes disposal asks scientific and public acceptance problems. This paper describes several aspects: technical problem; ethic problem and responsibility towards future generations at very long-term; political problem. Different politics followed by concerned countries and recent controversy in France is also entered upon radioactive wastes underground site selection, in deep geological formations.

GEO-ECOLOGICAL PROBLEMS OF DRILLING WASTE DISPOSAL IN THE YAMAL PENINSULA

Directory of Open Access Journals (Sweden)

Oreshkin Dmitrij Vladimirovich

2012-10-01

Full Text Available Crude oil and gas fields are located in remote areas known for their severe geological and climatic conditions that are aggravated by the presence of the paleocrystic frozen rock. Borehole drilling causes generation of the substantial amount of drilling waste. The sludge weighs millions of tons. Any rock is to remain frozen at any drilling site in the Yamal peninsula. Semifluid drilling waste occupies extensive areas around drilling sites; they prevent development of the surface infrastructure, they interfere with the work of drilling technicians and contribute to hazardous working conditions, they are a challenge to the local ecology. The above factors produce a negative impact on the environment and prevent sustainable development of the region. For example, disposal of drilling waste at condensed gas fields operated in the Yamal peninsula represents a substantial problem. Drilling waste contains drilling fluid used in the process of borehole drilling. It was discovered in the course of the preliminary research that drilling fluids were composite suspensions that contained bentonite, heavy spar, caustic soda, dilutants, and polymers. It was found out that the sludge was composed of silica, calcite, dolomite, aragonite, magnesite, some feldspars, heavy spar, gypsum and anhydrite, micas, hydromicas, clay minerals. Projections provided in the paper say that pre-neutralized sludge may be used in the manufacturing of building materials, such as bricks, claydite, small-size building units, etc. The authors argue that further research of the sludge elements and microstructure, as well as its chemical, mineral, granulometric and X-ray phase analyses need to be performed.

Research on near-surface disposal of very low level radioactive waste

International Nuclear Information System (INIS)

Wang Shaowei; Yue Huiguo; Hou Jie; Chen Haiying; Zuo Rui; Wang Jinsheng

2012-01-01

Radioactive waste disposal is one of the most sensitive environmental problems to control and solve. As the arriving of decommissioning of early period nuclear facilities in China, large amounts of very low level radioactive waste will be produced inevitably. The domestic and abroad definitions about very low level radioactive waste and its disposal were introduced, and then siting principles of near-surface disposal of very low level radioactive waste were discussed. The near- surface disposal siting methods of very low level radioactive waste were analyzed from natural and geographical conditions assessment, geological conditions analysis, hydrogeological conditions analysis, geological hazard assessment and radioactive background investigation; the near-surface disposal sites'natural barriers of very low level radioactive waste were analyzed from the crustal structure and physico-chemical characteristics, the dynamics characteristics of groundwater, the radionuclide adsorption characteristics of natural barriers and so on; the near-surface disposal sites' engineered barriers of very low level radioactive waste were analyzed from the repository design, the repository barrier materials selection and so on. Finally, the improving direction of very low level radioactive waste disposal was proposed. (authors)

Disposal Concepts for Radioactive Waste. Final Report of the Expert Group on Disposal Concepts for Radioactive Waste (EKRA)

International Nuclear Information System (INIS)

Wildi, Walter; Dermange, Francois; Appel, Detlef; Buser, Marcos; Eckhardt, Anne; Hufschmied, Peter; Keusen, Hans-Rudolf; Aebersold, Michael

2000-01-01

At the beginning of 1999, talks between the Swiss Federal Government, the siting Cantons (Cantons in which nuclear power plants are located and Canton Nidwalden), environmental organisations and the nuclear power plant operators on the lifetime of the existing power plants and solution of the waste management problem failed to reach a satisfactory outcome. In view of this, the Head of the Federal Department for the Environment, Transport, Energy and Communication (UVEK) decided to set up the Expert Group on Disposal Concepts for Radioactive Waste (EKRA) in June 1999. EKRA then worked on providing the background for a comparison of different waste management concepts. The group developed the concept of monitored long-term geological disposal and compared this with geological disposal, interim storage and indefinite storage. The aspects of active and passive safety, monitoring and control, as well as retrievability of waste were at the fore-front of these deliberations. This report presents the conclusions and recommendations of EKRA

Disposal Concepts for Radioactive Waste. Final Report of the Expert Group on Disposal Concepts for Radioactive Waste (EKRA)

Energy Technology Data Exchange (ETDEWEB)

Wildi, Walter; Dermange, Francois [Univ. of Geneva, CH-1211 Geneva (Switzerland); Appel, Detlef [PanGeo, Hannover (Germany); Buser, Marcos [Buser and Finger, Zurich (Switzerland); Eckhardt, Anne [Basler and Hofmann, Zurich (Switzerland); Hufschmied, Peter [Emch and Berger, Bern (Switzerland); Keusen, Hans-Rudolf [Geotest, Zollikofen (Switzerland); Aebersold, Michael [Swiss Federal Office of Energy (BFE), CH-3003 Bern (Switzerland)

2000-01-15

At the beginning of 1999, talks between the Swiss Federal Government, the siting Cantons (Cantons in which nuclear power plants are located and Canton Nidwalden), environmental organisations and the nuclear power plant operators on the lifetime of the existing power plants and solution of the waste management problem failed to reach a satisfactory outcome. In view of this, the Head of the Federal Department for the Environment, Transport, Energy and Communication (UVEK) decided to set up the Expert Group on Disposal Concepts for Radioactive Waste (EKRA) in June 1999. EKRA then worked on providing the background for a comparison of different waste management concepts. The group developed the concept of monitored long-term geological disposal and compared this with geological disposal, interim storage and indefinite storage. The aspects of active and passive safety, monitoring and control, as well as retrievability of waste were at the fore-front of these deliberations. This report presents the conclusions and recommendations of EKRA.

Refrigerators with chlorofluorohydrocarbon - always a problem. Why chlorofluorohydrocarbons are still an issue; Kuehlgeraete mit FCKW immer ein Problem. Warum Fluorchlorkohlenwasserstoffe noch ein Thema sind

Energy Technology Data Exchange (ETDEWEB)

Schnepel, Christiane

2009-05-15

The report discusses the following questions: What are CFCs and what is the environmental impact? Why is there still a CFCs problem in spite of the prohibition? Why is it so important to dispose old refrigerators in an appropriate way? What is the appropriate way for refrigerator disposal? What are the cost for refrigerator disposal and who is paying? What is the mass throughput balance and why is this value not suitable as control instrument? Which problems arise during disposal? What is the solution: where are we and what is the future?.

The legal system of nuclear waste disposal

International Nuclear Information System (INIS)

Dauk, W.

1983-01-01

This doctoral thesis presents solutions to some of the legal problems encountered in the interpretation of the various laws and regulations governing nuclear waste disposal, and reveals the legal system supporting the variety of individual regulations. Proposals are made relating to modifications of problematic or not well defined provisions, in order to contribute to improved juridical security, or inambiguity in terms of law. The author also discusses the question of the constitutionality of the laws for nuclear waste disposal. Apart from the responsibility of private enterprise to contribute to safe treatment or recycling, within the framework of the integrated waste management concept, and apart from the Government's responsibility for interim or final storage of radioactive waste, there is a third possibility included in the legal system for waste management, namely voluntary measures taken by private enterprise for radioactive waste disposal. The licence to be applied for in accordance with section 3, sub-section (1) of the Radiation Protection Ordinance is interpreted to pertain to all measures of radioactive waste disposal, thus including final storage of radioactive waste by private companies. Although the terminology and systematic concept of nuclear waste disposal are difficult to understand, there is a functionable system of legal provisions contained therein. This system fits into the overall concept of laws governing technical safety and safety engineering. (orig./HSCH) [de

Execution techniques for high-level radioactive waste disposal. 2. Fundamental concept of geological disposal and implementing approach of disposal project

International Nuclear Information System (INIS)

Kawanishi, Motoi; Komada, Hiroya; Tsuchino, Susumu; Shiozaki, Isao; Kitayama, Kazumi; Akasaka, Hidenari; Inagaki, Yusuke; Kawamura, Hideki

1999-01-01

The making high activity of the high-level radioactive waste disposal business shall be fully started after establishing of the implementing organization which is planned around 2000. Considering each step of disposal business, in this study, the implementation procedure for a series of disposal business such as the selection of the disposal site, the construction and operation of the disposal facility, the closure and decommissioning of the disposal facility and the management after closure, which are carried forward by the implementation body is discussed in detail from the technical viewpoint and an example of the master schedule is proposed. Furthermore, we investigate and propose the concept of the geological disposal which becomes important in carrying forward to making of the business of the disposal, such as the present site selection smoothly, the fundamental idea of the safe securing for disposal, the basic idea to get trust to the disposal technique and the geological environmental condition which is the basic condition of this whole study for the disposal business making. (author)

Methods of Disposing Of High-Level Radioactive Waste: A Review

International Nuclear Information System (INIS)

Abumurade, K.

2002-01-01

High level nuclear waste from both commercial reactors and defense industry presents a difficult problem to the scientific community as well as the public. The solutions to this problem is still debatable both technically and ethically. There are few methods proposed for disposing of high level waste. Each method has its own advantages and disadvantages. However, the very deep underground geologic repository is the best choice for disposing of high-level radioactive wastes. The cost benefit equation of nuclear power production and its waste is discussed. However, the public should be educated about this matter to minimize the gap between them and the nuclear power community including scientists industry, and governments. (Author) 15 refs., 4 tabs., 1 fig

A Portable Burn Pan for the Disposal of Excess Propellants

Science.gov (United States)

2016-06-01

2013 - 06/01/2016 A Portable Burn Pan for the Disposal of Excess Propellants Michael Walsh USA CRREL USA CRREL 72 Lyme Road Hanover, NH 03755...Army Alaska XRF X-Ray Florescence vii ACKNOWLEDGEMENTS Project ER-201323, A Portable Burn Pan for the Disposal of Gun Propellants, was a very...contamination problem while allowing troops to train as they fight, we have developed a portable training device for burning excess gun propellants. 1.1

Management and disposal of used nuclear fuel and reprocessing wastes

International Nuclear Information System (INIS)

1983-01-01

The subject is dealt with in chapters, entitled: introduction (general statement of problem); policy framework (criteria for waste management policy); waste management and disposal, as practised and planned (general; initial storage; reprocessing and conditioning of reprocessing wastes; intermediate storage; transportation; packaging; disposal); international co-operation. Details of the situation in each country concerned (Australia, Belgium, Canada, France, Federal Republic of Germany, Spain, Sweden, Switzerland and United Kingdom) are included as annexes. (U.K.)

Problems related to final disposal of high-level radioactive waste in Russia

International Nuclear Information System (INIS)

Velichkin, Vasily I.

1999-01-01

According to this presentation, the radioactivity of the total amount of radioactive waste accumulated in Russia to date is 1.5*10 9 Ci and of spent fuel 4.5*10 9 Ci. A table is given that shows the source, type, volume activity and storage type under the responsibility of the different departments and enterprises. 99.9% of the wastes are accumulated at the enterprises of Minatom of the Russian Federation. Some companies inject their liquid wastes from ionisation sources and intermediate liquid waste from the nuclear power industry into deep-seated reliably isolated aquifers. The Mayak plant has released liquid low-level and intermediate wastes into artificial reservoirs and Lake Karachay. Liquid high-level wastes are always stored in special tanks at interim storage facilities. A large number of nuclear submarines are laid up in North-Western Russia and East Russia, with spent fuel still in place as the interim storages in these regions are filled up and there are no conditioning plants. Underground disposal is considered the best way of isolating radioactive waste for as long as it is hazardous to the environment. Two new technologies are discussed. One involves including long-lived isotopes in high-stable mineral matrices, the other uses selective separation from the bulk of wastes. The matrices should be disposed of deep in the Earth's crust, at least 2-3 km down. Liquid waste of caesium-strontium fraction must be transformed into glass-like form and stored underground at a depth of a few hundred metres. Short-lived low level and intermediate level wastes should be conditioned and then deposited in subsurface ferroconcrete repositories constructed in clays. Finally, the presentation discusses the selection of sites and conditions for radioactive waste disposal. Two sites are discussed, the Mayak plant and a possible site at Mining Chemical Combine in Krasnoyarsk-26

Waste from medicine, industry and research must also be disposed of

International Nuclear Information System (INIS)

Issler, H.

1990-01-01

Disposal of waste in a manner which is environmentally acceptable is an important political concern of our society today. Nagra has been charged with the resposibility of solving this problem with respect to disposal of radioactive waste in particular. In this context, the fact that radioactive waste also arises from activities other than the operation of nuclear power plants is often overlooked. (author) 7 figs., 3 tabs

Differing approaches to waste disposal

International Nuclear Information System (INIS)

Greenhalgh, G.

1983-01-01

The social, political, and economic problems of radioactive waste management, which are discussed at a scientific afternoon meeting held during the IAEA general conference on 12 October, with speakers from Argentina, West Germany, France, India, Japan, Sweden, Britain and the United States, are described. An OECD Nuclear Energy Agency report on the demonstration of long-term safety of deep underground disposal of high level radioactive waste is discussed. (U.K.)

Selection of heat disposal methods for a Hanford Nuclear Energy Center

International Nuclear Information System (INIS)

Young, J.R.; Kannberg, L.D.; Ramsdell, J.V.; Rickard, W.H.; Watson, D.G.

1976-06-01

Selection of the best method for disposal of the waste heat from a large power generation center requires a comprehensive comparison of the costs and environmental effects. The objective is to identify the heat dissipation method with the minimum total economic and environmental cost. A 20 reactor HNEC will dissipate about 50,000 MWt of waste heat; a 40 reactor HNEC would release about 100,000 MWt. This is a much larger discharge of heat than has occurred from other concentrated industrial facilities and consequently a special analysis is required to determine the permissibility of such a large heat disposal and the best methods of disposal. It is possible that some methods of disposal will not be permissible because of excessive environmental effects or that the optimum disposal method may include a combination of several methods. A preliminary analysis is presented of the Hanford Nuclear Energy Center heat disposal problem to determine the best methods for disposal and any obvious limitations on the amount of heat that can be released. The analysis is based, in part, on information from an interim conceptual study, a heat sink management analysis, and a meteorological analysis

The residuals analysis project: Evaluating disposal options for treated mixed low-level waste

International Nuclear Information System (INIS)

Waters, R.D.; Gruebel, M.M.; Case, J.T.; Letourneau, M.J.

1997-01-01

For almost four years, the U.S. Department of Energy (DOE) through its Federal Facility Compliance Act Disposal Workgroup has been working with state regulators and governors' offices to develop an acceptable configuration for disposal of its mixed low-level waste (MLLW). These interactions have resulted in screening the universe of potential disposal sites from 49 to 15 and conducting ''performance evaluations'' for those fifteen sites to estimate their technical capabilities for disposal of MLLW. In the residuals analysis project, we estimated the volume of DOE's MLLW that will require disposal after treatment and the concentrations of radionuclides in the treated waste. We then compared the radionuclide concentrations with the disposal limits determined in the performance evaluation project for each of the fifteen sites. The results are a scoping-level estimate of the required volumetric capacity for MLLW disposal and the identification of waste streams that may pose problems for disposal based on current treatment plans. The analysis provides technical information for continued discussions between the DOE and affected States about disposal of MLLW and systematic input to waste treatment developers on disposal issues

Environmental problems caused by bituminous schist and possible solutions

International Nuclear Information System (INIS)

Elmas, N.; Aykul, H.; Erarslan, K.; Ediz, I.G.

1998-01-01

Schist, as a disposal of mine, has harmful effects on environment. however, several manners can be utilized to prevent the environmental destruction as well as an economical benefit is gained. In this study, environmental problems caused by bituminous schist and other disposals have been investigated on a specific lignite coal mine where schist is disposed as waste material. Pollution and damage on land and in water sources around the coal district and the villages have been observed, recorded and several solutions to environmental problems have been proposed. Discussed proposals will not only solve the environmental pollution problem but also provide waste management facility. Industrial structure of the district enables such a disposal to be used as an economical raw material. Besides, general effects of the coal mine and the power plant nearby have been discussed from environmental point of view, too. 7 refs

Recent development of International Commission of Radiation Protection about the radioactive waste disposal

International Nuclear Information System (INIS)

Cancio, David; Carboneras, Pedro

2001-01-01

ICRP has recently produced three Publications 77, 81 and 82 containing principles for disposal of radioactive waste, in order to complement its previous publication about this theme. The purpose of this paper was to describe the most relevant aspects of disposal presented in these three publications. The principles of management, optimization and dose limit were applied for radioactive waste disposal and the control of public exposure. This control has been defined to be done through the concepts of dose constraint, collective dose, potential exposures, intervention and protection of future generation. The problem of high-level radioactive waste and its disposal has been re-evaluated

Disposal safety

International Nuclear Information System (INIS)

Bartlett, J.W.

International consensus does not seem to be necessary or appropriate for many of the issues concerned with the safety of nuclear waste disposal. International interaction on the technical aspects of disposal has been extensive, and this interaction has contributed greatly to development of a consensus technical infrastructure for disposal. This infrastructure provides a common and firm base for regulatory, political, and social actions in each nation

French surface disposal experience. The disposal of large waste

International Nuclear Information System (INIS)

Dutzer, Michel; Lecoq, Pascal; Duret, Franck; Mandoki, Robert

2006-01-01

More than 90 percent of the volume of radioactive waste that are generated in France can be managed in surface disposal facilities. Two facilities are presently operated by ANDRA: the Centre de l'Aube disposal facility that is dedicated to low and intermediate short lived waste and the Morvilliers facility for very low level waste. The Centre de l'Aube facility was designed at the end of the years 1980 to replace the Centre de la Manche facility that ended operation in 1994. In order to achieve as low external exposure as possible for workers it was decided to use remote handling systems as much as possible. Therefore it was necessary to standardize the types of waste containers. But taking into account the fact that these waste were conditioned in existing facilities, it was not possible to change a major part of existing packages. As a consequence, 6 mobile roofs were constructed to handle 12 different types of waste packages in the disposal vaults. The scope of Centre de l'Aube was mainly to dispose operational waste. However some packages, as 5 or 10 m 3 metallic boxes, could be used for larger waste generated by decommissioning activities. The corresponding flow was supposed to be small. After the first years of operations, it appeared interesting to develop special procedures to dispose specific large waste in order to avoid external exposure costly cutting works in the generating facilities. A 40 m 3 box and a large remote handling device were disposed in vaults that were currently used for other types of packages. Such a technique could not be used for the disposal of vessel heads that were replaced in 55 pressurised water power reactors. The duration of disposal and conditioning operation was not compatible with the flow of standard packages that were delivered in the vaults. Therefore a specific type of vault was designed, including handling and conditioning equipment. The first pressure vessel head was delivered on the 29 of July 2004, 6 heads have been

The disposal of Canada's nuclear fuel waste: engineering for a disposal facility

International Nuclear Information System (INIS)

Simmons, G.R.; Baumgartner, P.

1994-01-01

This report presents some general considerations for engineering a nuclear fuel waste disposal facility, alternative disposal-vault concepts and arrangements, and a conceptual design of a used-fuel disposal centre that was used to assess the technical feasibility, costs and potential effects of disposal. The general considerations and alternative disposal-vault arrangements are presented to show that options are available to allow the design to be adapted to actual site conditions. The conceptual design for a used-fuel disposal centre includes descriptions of the two major components of the disposal facility, the Used-Fuel Packaging Plant and the disposal vault; the ancillary facilities and services needed to carry out the operations are also identified. The development of the disposal facility, its operation, its decommissioning, and the reclamation of the site are discussed. The costs, labour requirements and schedules used to assess socioeconomic effects and that may be used to assess the cost burden of waste disposal to the consumer of nuclear energy are estimated. The Canadian Nuclear Fuel Waste Management Program is funded jointly by AECL and Ontario Hydro under the auspices of the CANDU Owners Group. (author)

Radioactive wastes: sources, treatment, and disposal

International Nuclear Information System (INIS)

Wymer, R.G.; Blomeke, J.O.

1975-01-01

Sources, treatment, and disposal of radioactive wastes are analyzed in an attempt to place a consideration of the problem of permanent disposal at the level of established or easily attainable technology. In addition to citing the natural radioactivity present in the biosphere, the radioactive waste generated at each phase of the fuel cycle (mills, fabrication plants, reactors, reprocessing plants) is evaluated. The three treatment processes discussed are preliminary storage to permit decay of the short-lived radioisotopes, solidification of aqueous wastes, and partitioning the long-lived α emitters for separate and long-term storage. Dispersion of radioactive gases to the atmosphere is already being done, and storage in geologically stable structures such as salt mines is under active study. The transmutation of high-level wastes appears feasible in principle, but exceedingly difficult to develop

How to dispose of the other radwaste

International Nuclear Information System (INIS)

Anon.

1987-01-01

While the US Department of Energy searches for a repository for the highly radioactive spent fuel from nuclear power plants, federal law requires the states by January to have plans for establishing regional landfill sites for the disposal of so-called low-level radioactive waste. But a recent report from the Radioactive Waste Campaign in New York calls for ending the landfill approach to disposal of low-level waste in order to avoid the leakage and contamination of water supplies that have wracked existing landfills. According to physicist Marvin Resnikoff, author of the report, low-level waste is a misnomer for what often includes extremely long-lived radioactive waste requiring more careful disposal. Because 99% of the radioactivity and 70% of the volume of low-level waste comes from power reactors, Resnikoff advocates disposal on the plant site. He also advocates separation of wastes by their half-life and reclassification as high level of the long-lived radioactive waste from decommissioned plants. The much smaller volume of industrial and institutional waste should be supercompacted and also transferred to the plants for storage. The report further recommends a Manhattan Project-style effort to deal with the problem of radioactive waste as a whole

Final disposal of the rad waste materials - question of the nuclear energy implementation and application perspectives

International Nuclear Information System (INIS)

Plecas, I.

1995-01-01

Two main problems that are denying and slowing down the development of nuclear energy are safe work of the nuclear power facilities (NEF) and disposal of the radioactive waste materials, produced from the NEF and infrastructure facilities of the nuclear fuel cycle (NFC). Although nowadays worldwide knowledge, based on the 45 year of experiences in handling the radioactive waste materials, do not treat the problems of final disposal of the rad waste materials as a task of the primary importance in NFC, this subject still engage experts from this field of investigations, especially in the countries that developed all aspects of the nuclear fuel cycle. Techniques for final disposal of low and intermediate level rad waste materials, are well known and are in state of implementation. The importance of the fundamental safety principles, implemented in the IAEA documents, concerning handling, treatment and final disposal of the rad waste materials, is presented. Future usage of nuclear energy, taking into account all the facts that are dealing with problems of the rad waste materials produced in the NFC, can be a reality. (author.)

The problem of final storage of radioactive waste - ethical considerations of the goods and evils

International Nuclear Information System (INIS)

Korff, W.; Feldhaus, S.

1996-01-01

The handling of radioactive remains proves to be separate, by now increasingly dominating problem in the discussion about nuclear energy. The application of the practical and concrete-ethical methodology of deliberation on goods and evils to the problems of permanent disposal, which is systematically expounded in the text, was able to show the following: 1. In the judgement on permanent disposal of nuclear waste we have to do with a prcedural-ethical process of deliberation as well. A morally justifiable and therefore responsible handling of our options has to be carried out in context of the individual, social and ecological requirements of the day as a continuous process of optimisation. Everywhere findable, on principle orientated attitudes of refusal against deliberation don't constitute an adequate solution of the problem. 2. The problems of permanent disposal have to be considered in the all-embracing context of the problems of waste disposal, in that occasion the waste disposal form of reprocessing has to be included into deliberation apart from that one of interim diposal, which is normally placed before permanent disposal. 3. The issue of permanent disposal can be discussed only in the extensive context of nuclear energy use and the problems of its ethical legitimation. 4. The problems of social acceptance of the nuclear energy use, fixed today essentially to the issue of permanent disposal of radioactive remains, cannot be easily equated with the question for its ehtical justification. (orig.) [de

Study on the development of safety regulations for geological disposal of high-level radioactive waste

International Nuclear Information System (INIS)

Wei Fangxin

2012-01-01

The development of regulations under Regulations on Safety Management of Radioactive Waste has become necessary as the issuance of it. The regulations related to geological disposal of high-level radioactive waste can promote the progress of research and development on geological disposal of high-level radioactive waste in China. This paper has present suggestions on development of regulations on geological disposal of high-level radioactive waste by analyzing development of safety regulations on geological disposal of high-level radioactive waste in foreign countries and problems occurred in China and discussed important issues related to the development of safety regulations on geological disposal of high-level radioactive waste. (author)

Role of the unsaturated zone in radioactive and hazardous waste disposal

International Nuclear Information System (INIS)

Mercer, J.W.; Marine, I.W.; Rao, P.S.C.

1983-01-01

The problems of hazardous and low-level radioactive waste disposal caused by the physical and chemical processes active in the unsaturated zone are explored in this book. The focus is on the use of laboratory analyses, field observations, and numerical and analytical calculations to create a clear picture of both problems and potential solutions. Topics include policy modeling, statistical techniques, liners, and field applications. Contents include: Modeling of Moisture Movement through Layered Trench Covers; Role of Partially Saturated Soil in Liner Design for Hazardous Waste Disposal Sites; Field Experiments to Determine Saturated Hydraulic Conductivity in the Vadose Zone; Role of Desaturation on Transport through Fractured Rock; Nuclear Waste Isolation in the Unsaturated Zone of Arid Regions

Alternative Concept to Enhance the Disposal Efficiency for CANDU Spent Fuel Disposal System

International Nuclear Information System (INIS)

Lee, Jong Youl; Cho, Dong Geun; Kook, Dong Hak; Lee, Min Soo; Choi, Heui Joo

2011-01-01

There are two types of nuclear reactors in Korea and they are PWR type and CANDU type. The safe management of the spent fuels from these reactors is very important factor to maintain the sustainable energy supply with nuclear power plant. In Korea, a reference disposal system for the spent fuels has been developed through a study on the direct disposal of the PWR and CANDU spent fuel. Recently, the research on the demonstration and the efficiency analyses of the disposal system has been performed to make the disposal system safer and more economic. PWR spent fuels which include a lot of reusable material can be considered being recycled and a study on the disposal of HLW from this recycling process is being performed. CANDU spent fuels are considered being disposed of directly in deep geological formation, since they have little reusable material. In this study, based on the Korean Reference spent fuel disposal System (KRS) which was to dispose of both PWR type and CANDU type, the more effective CANDU spent fuel disposal systems were developed. To do this, the disposal canister for CANDU spent fuels was modified to hold the storage basket for 60 bundles which is used in nuclear power plant. With these modified disposal canister concepts, the disposal concepts to meet the thermal requirement that the temperature of the buffer materials should not be over 100 .deg. C were developed. These disposal concepts were reviewed and analyzed in terms of disposal effective factors which were thermal effectiveness, U-density, disposal area, excavation volume, material volume etc. and the most effective concept was proposed. The results of this study will be used in the development of various wastes disposal system together with the HLW wastes from the PWR spent fuel recycling process.

Sewage sludge treatment, utilisation and disposal; Schlammbehandlung, -verwertung und -beseitigung

Energy Technology Data Exchange (ETDEWEB)

NONE

2004-07-01

In view of recent events and the resulting emotional and political decisions, the issue of sewage sludge treatment and disposal in Germany. must be seen in a new light. First, a new concept for sewage sludge management must be developed as recent legislation interferes with the 'classic' strategy of utilisation in agriculture, dumping and combustion. Scientists and sewage plant owners must find new ways to implement the specifications of the Act on Recycling and Waste Management. This ATV-DVWK training course discusses subjects that may be helpful on the new path. Starting from current legislation, problems, decision criteria and cost of sewage sludge treatment are gone into. Dimensioning fundamentals for sewage treatment plants re presented, and new and established treatment methods, operational problems and pollution problems are discussed. Further subjects are recycling of useful materials from sewage sludge, co-treatment of organic materials in fermenters, and disposal concepts for small and medium-sized communities. (orig.)

Illinois perspective on low level radioactive waste disposal

International Nuclear Information System (INIS)

Etchison, D.

1984-01-01

Illinois is a big generator of low level radioactive waste. It has had extensive experience with controversial waste disposal and storage facilities. This experience makes it difficult for the public and political leaders in Illinois to support the establishment of new disposal facilities in the state. Yet, with extensive debates and discussions concerning the Low Level Waste Policy Act of 1980 and the proposed Midwest Compact, political leaders and the public are facing up to the fact that they must be responsible for the disposal of the low level radioactive waste generated in the state. The Governor and many political leaders from Illinois support the regional approach and believe it can be an innovative and progressive way for the state to deal with the range of low level waste management and disposal problems. A version of the Midwest Interstate Low Level Waste Compact has become Illinois law, but it has significant differences from the one adopted by five other states. Like other states in the midwest and northeast, Illinois is opposed to Congressional consent of the four pending compacts before the remaining two compacts, the northeast and midwest are sent to Washington and interregional agreements are negotiated between the sited and non-sited regions. A new national system must be established before access to existing commercial disposal becomes restricted

Waste disposal experts meet

Energy Technology Data Exchange (ETDEWEB)

NONE

1959-01-15

Problems connected with the disposal into the sea of radioactive wastes from peaceful uses of atomic energy are being examined by a panel of experts, convened by the International Atomic Energy Agency. These experts from eight different countries held a first meeting at IAEA headquarters in Vienna from 4-9 December 1958, under the chairmanship of Dr. Harry Brynielsson, Director General of the Swedish Atomic Energy Company. The countries represented are: Canada, Czechoslovakia, France, Japan, Netherlands, United Kingdom and United States. The group will meet again in 1959. (author)

Self-disposal option for heat-generating waste - 59182

International Nuclear Information System (INIS)

Ojovan, Michael I.; Poluektov, Pavel P.; Kascheev, Vladimir A.

2012-01-01

Self-descending heat generating capsules can be used for disposal of dangerous radioactive wastes in extremely deep layers of the Earth preventing any release of radionuclides into the biosphere. Self-disposal option for heat-generating radioactive waste such as spent fuel, high level reprocessing waste or spent sealed radioactive sources, known also as rock melting concept, was considered in the 70's as a viable alternative disposal option by both Department of Energy in the USA and Atomic Industry Ministry in the USSR. Self-disposal is currently reconsidered as a potential alternative route to existing options for solving the nuclear waste problem and is associated with the renaissance of nuclear industry. Self- disposal option utilises the heat generated by decaying radionuclides of radioactive waste inside a heavy and durable capsule to melt the rock on its way down. As the heat from radionuclides within the capsule partly melts the enclosing rock, the relatively low viscosity and density of the silicate melt allow the capsule to be displaced upwards past the heavier capsule as it sinks. Eventually the melt cools and solidifies (e.g. vitrifies or crystallizes), sealing the route along which the capsule passed. Descending or self-disposal continues until enough heat is generated by radionuclides to provide partial melting of surrounding rock. Estimates show that extreme depths of several tens and up to hundred km can be reached by capsules which could never be achieved by other techniques. Self- disposal does not require complex and expensive disposal facilities and provides a minimal footprint used only at operational stage. It has also an extremely high non- proliferation character and degree of safety. Utilisation of heat generated by relatively short-lived radionuclides diminishes the environmental uncertainties of self-disposal and increases the safety of this concept. Self-sinking heat-generating capsules could be launched from the bottom of the sea as

A laboratory evaluation of two brands of disposable air turbine handpiece.

Science.gov (United States)

Dyson, J E; Darvell, B W

1997-01-11

To report on the essential performance characteristics of two brands of disposable air turbine handpiece and on aspects of their safety and convenience for clinical use. Oralsafe and Feathertouch disposable handpieces were characterised using a variety of techniques in respect of the following: turbine rotor radius, equivalent orifice radius, stall torque coefficient, pressure effectiveness, power index, efficiency index, sound level and instrument retention force. Free-running speed versus pressure curves for many of the disposable handpieces showed marked deviations from the expected smooth form. Considerable variation between examples of each type was found in most measured values. Evidence of eccentric rotors and high bearing friction was not found. Both brands of disposable handpiece had a number of problems: poor performance, vibration, excessive noise, variability of behaviour, poor bearings. Use of these devices is difficult to recommend. Improvement in design seems necessary.

Low level waste disposal

International Nuclear Information System (INIS)

Barthoux, A.

1985-01-01

Final disposal of low level wastes has been carried out for 15 years on the shallow land disposal of the Manche in the north west of France. Final participant in the nuclear energy cycle, ANDRA has set up a new waste management system from the production center (organization of the waste collection) to the disposal site including the setting up of a transport network, the development of assessment, additional conditioning, interim storage, the management of the disposal center, records of the location and characteristics of the disposed wastes, site selection surveys for future disposals and a public information Department. 80 000 waste packages representing a volume of 20 000 m 3 are thus managed and disposed of each year on the shallow land disposal. The disposal of low level wastes is carried out according to their category and activity level: - in tumuli for very low level wastes, - in monoliths, a concrete structure, of the packaging does not provide enough protection against radioactivity [fr

Alternative disposal options for alpha-mixed low-level waste

International Nuclear Information System (INIS)

Loomis, G.G.; Sherick, M.J.

1995-01-01

This paper presents several disposal options for the Department of Energy alpha-mixed low-level waste. The mixed nature of the waste favors thermally treating the waste to either an iron-enriched basalt or glass waste form, at which point a multitude of reasonable disposal options, including in-state disposal, are a possibility. Most notably, these waste forms will meet the land-ban restrictions. However, the thermal treatment of this waste involves considerable waste handling and complicated/expensive offgas systems with secondary waste management problems. In the United States, public perception of offgas systems in the radioactive incinerator area is unfavorable. The alternatives presented here are nonthermal in nature and involve homogenizing the waste with cryogenic techniques followed by complete encapsulation with a variety of chemical/grouting agents into retrievable waste forms. Once encapsulated, the waste forms are suitable for transport out of the state or for actual in-state disposal. This paper investigates variances that would have to be obtained and contrasts the alternative encapsulation idea with the thermal treatment option

Alternative disposal options for alpha-mixed low-level waste

Energy Technology Data Exchange (ETDEWEB)

Loomis, G.G.; Sherick, M.J. [Idaho National Engineering Lab., Idaho Falls, ID (United States)

1995-12-31

This paper presents several disposal options for the Department of Energy alpha-mixed low-level waste. The mixed nature of the waste favors thermally treating the waste to either an iron-enriched basalt or glass waste form, at which point a multitude of reasonable disposal options, including in-state disposal, are a possibility. Most notably, these waste forms will meet the land-ban restrictions. However, the thermal treatment of this waste involves considerable waste handling and complicated/expensive offgas, systems with secondary waste management problems. In the United States, public perception of off gas systems in the radioactive incinerator area is unfavorable. The alternatives presented here are nonthermal in nature and involve homogenizing the waste with cryogenic techniques followed by complete encapsulation with a variety of chemical/grouting agents into retrievable waste forms. Once encapsulated, the waste forms are suitable for transport out of the state or for actual in-state disposal. This paper investigates variances that would have to be obtained and contrasts the alternative encapsulation idea with the thermal treatment option.

Current researches on safety assessment of radioactive waste disposal in the United States

International Nuclear Information System (INIS)

Tasaka, Hiroshi; Kiyose, Ryohei

1980-01-01

Recently, the problem of safe disposal of radioactive waste generated from nuclear fuel cycle becomes more important in Japan. On the other hand, many researches on shallow land burial of low-level wastes and geologic isolation of high-level wastes have been carried out in the United States of America. In this report, the researches on the safety assessment of radioactive waste disposal in the United States of America were briefly introduced with emphasis on the studies on behavior and migration of radionuclide from disposed waste in geosphere. (author)

Assumption and program of the earlier stage construction of L/ILW disposal site

International Nuclear Information System (INIS)

Li Xuequn; Chen Shi; Li Xinbang

1993-01-01

The authors analysed the production and treatment of low- and intermediate-level radwastes (L/ILW) in China. Some problems and situation in this field are introduced. Over the past ten years, preliminary efforts have been made by CNNC (China National Nuclear Corporation) in policy, law and rules, developing program, management system, siting, engineering techniques, and safety assessment for radwaste disposal. The investment of the earlier stage work of L/ILW disposal site construction is estimated, the program and assumption to disposal site construction of the L/ILW are reviewed

Economic and energy analysis about disposal interventions of waste tires produced in Calabria

International Nuclear Information System (INIS)

Florio, Gaetano; Cersosimo, Attilio.

1997-01-01

The present paper refers to an analysis aimed at researching disposal strategies, for waste tires produced in Calabria, which ensure correct disposal with regard to environmental compatibility and their evaluation in terms of material recovery and energy. The starting point has been an estimate of the quantities of potentially usable waste tires and disposal methods currently employed. It has therefore been possible to identify two specific disposal proposals for which an economic and energy evaluation has been conducted. The last part of the paper has faced the problem of plant location under consideration, with the aim of determining, for both proposal, the cost that each producer must bear to have his waste tires eliminated

Nuclear waste - the unsolved problem

International Nuclear Information System (INIS)

Boyle, S.

1986-01-01

Nuclear waste is identified and the problems created by reprocessing are mentioned. The disposal option for low, intermediate and high-level radioactive wastes are discussed. Sites where disposal has taken place have been found to be unsatisfactory because of contamination and radionuclide migration. The Nuclear Industry Radioactive Waste Executive (NIREX) is not seen as having any more credibility than the other nuclear authorities involved (BNFL, UKAEA, CEGB). Until an adequate, publically acceptable, method of disposing of the wastes already created has been found the author states that no more should be created. (U.K.)

Waste disposal

International Nuclear Information System (INIS)

Neerdael, B.; Marivoet, J.; Put, M.; Verstricht, J.; Van Iseghem, P.; Buyens, M.

1998-01-01

The primary mission of the Waste Disposal programme at the Belgian Nuclear Research Centre SCK/CEN is to propose, develop, and assess solutions for the safe disposal of radioactive waste. In Belgium, deep geological burial in clay is the primary option for the disposal of High-Level Waste and spent nuclear fuel. The main achievements during 1997 in the following domains are described: performance assessment, characterization of the geosphere, characterization of the waste, migration processes, underground infrastructure

Waste disposal

International Nuclear Information System (INIS)

2005-01-01

Radioactive waste, as a unavoidable remnant from the use of radioactive substances and nuclear technology. It is potentially hazardous to health and must therefore be managed to protect humans and the environment. The main bulk of radioactive waste must be permanently disposed in engineered repositories. Appropriate safety standards for repository design and construction are required along with the development and implementation of appropriate technologies for the design, construction, operation and closure of the waste disposal systems. As backend of the fuel cycle, resolving the issue of waste disposal is often considered as a prerequisite to the (further) development of nuclear energy programmes. Waste disposal is therefore an essential part of the waste management strategy that contributes largely to build confidence and helps decision-making when appropriately managed. The International Atomic Energy Agency provides assistance to Member States to enable safe and secure disposal of RW related to the development of national RWM strategies, including planning and long-term project management, the organisation of international peer-reviews for research and demonstration programmes, the improvement of the long-term safety of existing Near Surface Disposal facilities including capacity extension, the selection of potential candidate sites for different waste types and disposal options, the characterisation of potential host formations for waste facilities and the conduct of preliminary safety assessment, the establishment and transfer of suitable technologies for the management of RW, the development of technological solutions for some specific waste, the building of confidence through training courses, scientific visits and fellowships, the provision of training, expertise, software or hardware, and laboratory equipment, and the assessment of waste management costs and the provision of advice on cost minimisation aspects

Patients’ Knowledge of and Practices Relating to the Disposal of Used Insulin Needles

Directory of Open Access Journals (Sweden)

Kerri T. Musselman, PharmD

2010-01-01

Full Text Available Objective: To determine (1 how patients currently dispose of used insulin needles, (2 whether patients were educated about disposal of their used insulin needles, and (3 who educated patients about the disposal of their used insulin needles.Methods: A self-administered questionnaire was designed for this study. The survey assessed patient knowledge about disposal of used insulin needles and the patient-reported source and location of education about disposal techniques. The questionnaire was administered to a convenience sample of patients from four locations in Richmond, Virginia. Any patient who used insulin, was at least 18 years old, and was willing to complete the survey was eligible for inclusion.Results: Fifty responses were received with 40% indicating that education had been received on the disposal of used needles. From that 40%, nurses were identified as the source of education 60% of the time and pharmacists 25% of the time. Approximately 50% of the respondents reported disposing of used needles directly in the trash when at home. While away from home, 22% reported placing used needles in the trash, and 38% took them home for disposal.Conclusion: Patients are not consistently educated regarding the proper disposal of used needles. Health care practitioners should play a larger role in educating patients about the potential risks of inappropriate needle disposal and appropriate disposal methods. Future research is still needed to understand fully the magnitude of the problems associated with inappropriate needle disposal by patients.

Household Hazardous Waste Disposal Project. Summary Report. Metro Toxicant Program Report No. 1A.

Science.gov (United States)

Ridgley, Susan M.; Galvin, David V.

The Household Hazardous Waste Disposal Project was established as an interagency effort to reduce the level of toxicants entering the environment by developing a control plan for the safe disposal of small quantities of household chemicals. This summary report provides an overview of the aspects of this problem that were examined, and the steps…

Harmful effects of wastewater disposal into water bodies: a case ...

African Journals Online (AJOL)

Improper disposal of waste water and the problems of addressing ... Abattoir wastes, industrial wastes from breweries, agricultural runoffs, and waste water from ... Ni and Pb make such water unsuitable for drinking, irrigation, aquatic life and ...

The disposal of orphan wastes using the greater confinement disposal concept

International Nuclear Information System (INIS)

Bonano, E.J.; Chu, M.S.Y.; Price, L.L.; Conrad, S.H.; Dickman, P.T.

1991-01-01

In the United States, radioactive wastes are conventionally classified as high-level wastes, transuranic wastes, or low-level wastes. Each of these types of wastes, by law, has a ''home'' for their final disposal; i.e., high-level wastes are destined for disposal at the proposed repository at Yucca Mountain, transuranic waste for the proposed Waste Isolation Pilot Plant, and low-level waste for shallow-land disposal sites. However, there are some radioactive wastes within the United States Department of Energy (DOE) complex that do not meet the criteria established for disposal of either high-level waste, transuranic waste, or low-level waste. The former are called ''special-case'' or ''orphan'' wastes. This paper describes an ongoing project sponsored by the DOE's Nevada Operations Office for the disposal of orphan wastes at the Radioactive Waste Management Site at Area 5 of the Nevada Test Site using the greater confinement disposal (GCD) concept. The objectives of the GCD project are to evaluate the safety of the site for disposal of orphan wastes by assessing compliance with pertinent regulations through performance assessment, and to examine the feasibility of this disposal concept as a cost-effective, safe alternative for management of orphan wastes within the DOE complex. Decisions on the use of GCD or other alternate disposal concepts for orphan wastes be expected to be addressed in a Programmatic Environmental Impact Statement being prepared by DOE. The ultimate decision to use GCD will require a Record of Decision through the National Environmental Policy Act (NEPA) process. 20 refs., 3 figs., 2 tabs

Development of an integrated software system (Digital Geological Disposal System) for design and evaluation of HLW disposal system

International Nuclear Information System (INIS)

Fusaeda, Shigeki; Yanagisawa, Ichiro; Imamura, Naoko

2000-02-01

In this study, a design study on 'Digital Geological Disposal System' has been carried out in order to define the developmental goal for the first phase (- FY2002) system and to demonstrate the feasibility of the system development. The key conclusions are summarized as follows: (1) As the result of the basic design of the Integrated Analysis Platform (IAP), the representation method for PLAN (Process Linkage Analysis Network), the PLAN objects configuration and definition and the execution control mechanism of PLAN are newly proposed in order to enhance the flexibility of IAP. (2) A prototyping study concerning an optimization problem that includes cavity stability analysis and thermal analysis, showed that the design of IAP is practical one and also has enough flexibility to solve complex problems expected in the repository design processes. (3) The development plan for the Digital Geological Disposal System' has been investigated based on the discussions about the system usage by the potential users such as the regulators, the implementation body and the research institutes, as well as the technical discussions. As a result, short-term (for the first phase) and long-term development plans have been proposed. (author)

Disposal of high level radioactive waste consideration of some basic criteria

International Nuclear Information System (INIS)

1993-01-01

The series of Nordic documents on radiation protection principles present the joint views of the Nordic authorities on radiation protection issues. These views are to be regarded as recommendations to the same Nordic authorities to be considered in their work on national regulations and applications. This document deals with the principles of disposal of high level radioactive waste, including spent fuels, and is therefore intended for authorities in nuclear safety as well as radiation protection. The emphasis is on radiation protection criteria, and the document is primarily directed to the authorities but can also be of interest to the nuclear power industry in its planning of disposal facilities. It can also be used as a source of information on the problems associated with high level waste and on the principles by which these problems would be solved. The main emphasis has been placed on the long-term aspects. The recommendations given by ICRP and the ideas and discussions presented by NEA and IAEA in various publications were the main documents taken into account. The discussions concentrate on the deep geological repository which is the main disposal concept currently being considered in the Nordic countries. The plans in Finland and Sweden include the selection of a disposal site around the year 2000 and a construction period in the early part of the next century. 32 refs, 3 figs

Trench design and construction techniques for low-level radioactive waste disposal

International Nuclear Information System (INIS)

Tucker, P.G.

1983-02-01

This document provides information on trench design and construction techniques which can be used in the disposal of LLW by shallow land burial. It covers practices currently in use not only in the LLW disposal field, but also methods and materials being used in areas of hazardous and municipal waste disposal which are compatible with the performance objectives of 10 CFR Part 61. The complexity of a disposal site and its potential problems dictate the use of site-specific characteristics when designing a LLW disposal trench. This report presents the LLW disposal trench as consisting of various elements or unit processes. The term unit processes is used as it more fully relays the impact of the designer's choice of methods and materials. When choosing a material to fulfill the function of a certain trench element, the designer is also stipulating a portion of his operational procedure which must be compatible with the disposal operation as a whole. Information is provided on the properties, selection, and installation of various materials such as bentonite, soil-cement, polymeric materials, asphaltic materials, and geotechnical fabrics. This is not intended to outline step-by-step procedures. Basically, three time frames are addressed with respect to construction techniques; preoperational, operational, and postoperational. Within each of these time frames there are certain construction techniques which can be employed by the designer to enhance the overall ease of construction and ultimate success of the disposal facility. Among the techniques presented are precontouring the disposal area, alignment of the trench axis, sloping the trench bottom, incremental excavation, and surface water (runoff) management

Disposal of high level nuclear wastes: Thermodynamic equilibrium and environment ethics

Institute of Scientific and Technical Information of China (English)

RANA Mukhtar Ahmed

2009-01-01

Contamination of soil, water or air, due to a failure of containment or disposal of high level nuclear wastes, can potentially cause serious hazards to the environment or human health. Essential elements of the environment and radioactivity dangers to it are illustrated. Issues of high level nuclear waste disposal are discussed with a focus on thermodynamic equilibrium and environment ethics. Major aspects of the issues are analyzed and described briefly to build a perception of risks involved and ethical implications. Nuclear waste containment repository should be as close as possible to thermodynamic equilibrium. A clear demonstration about safety aspects of nuclear waste management is required in gaining public and political confidence in any possible scheme of permanent disposal. Disposal of high level nuclear waste offers a spectrum of environment connected challenges and a long term future of nuclear power depends on the environment friendly solution of the problem of nuclear wastes.

Some legal aspects on high level radioactive waste disposal in Japan

International Nuclear Information System (INIS)

Tanabe, Tomoyuki

1997-01-01

In Japan, it is considered to be an urgent problem to prepare the system for the research and execution of high level radioactive waste disposal. Under what regulation scheme the disposal should be done has not been sufficiently examined. In this research, the examination was carried out on the legal aspects of high level radioactive waste disposal as follows. First, the current legislation on the disposal in Japan was analyzed, and it was made clear that high level radioactive waste disposal has not been stipulated clearly. Next, on the legal choices which are conceivable on the way the legislation for high level radioactive waste disposal should be, from the aspects of applying the law on regulating nuclear reactors and others, applying the law on nuclear power damage reparation, and industrialization by changing the government ordinances, those were arranged in six choices, and the examination was carried out for each choice from the viewpoints of the relation with the base stipulation for waste-burying business, the speciality of high level radioactive waste disposal as compared with other actions of nuclear power business, the coordination with existing nuclear power of nuclear power business, the coordination with existing nuclear power law system and the formation of national consensus. In this research, it was shown that the execution of high level radioactive waste disposal as the business based on the separate legislation is the realistic choice. (K.I.)

New state roles in the management and disposal of commercial nuclear waste

International Nuclear Information System (INIS)

Udall, M.K.

1977-01-01

Arguments are presented for the need for congressional action to clarify the respective regulatory responsibilities of the state and Federal Governments as they relate to commercial nuclear power. Three case studies in radioactive waste management and disposal are reviewed which are proported to illustrate the inadequacy of the existing regulatory framework to effectively manage and dispose of nuclear wastes. Examples of instances in which state legislatures have taken the initiative in the waste disposal problem are cited. It is concluded that regulatory reform should be in the direction of a dual system that provides states with new authority and leverage to control nuclear energy development patterns within their borders

An eco friendly solution to the food waste disposal

Science.gov (United States)

Babu, G. Reddy; Kumar, G. Madhav

2017-07-01

In recent years, waste disposal at workmen camp is one of the major problems being faced by many nations across the world. In the workmen colony at Chittapur, a series of kitchens were built for cooking purpose and a number of small canteens are also functioning. Considerable quantity of food waste is collected daily from these eateries and disposed at a faraway place. Food waste is highly degradable in nature, if not disposed properly it causes problems related to environmental pollution. Hence, it is very important to identify an environment friendly process rather than opt for land filling or any disposal method. We worked together to find a suitable eco-friendly solution for the food waste disposal at Chittapur site and suggested that biogas production through anaerobic digestion is a solution for the disposal and utilization of food waste for better purpose. This resulted in setting up a 500 kg per day food waste treatment biogas plant at Chittapur. This establishment is the first time in the construction industry at workmen camp in India. Anaerobic Digestion has been recognized as one of the best options that is available for treating food waste, as it generates two valuable end products, biogas and compost. Biogas is a mixture of CH4 and CO2 about (55:45). Biogas generated can be used for thermal applications such as cooking or for generating electricity. The digested slurry is a well stabilized organic manure and can be used as soil fertilizer. Plant design is to handle 500 kg of food waste /day. 27 kg LPG is obtained from 500kg of kitchen waste. The Value of 27 kg of LPG is Rs.2700/day. Daily 1000 litres of digested effluent was obtained. It is good organic manure with plant micro nutrients and macro nutrients. This can be used for growing plants and in agriculture. The value of manure per day is Rs.250/-. The annual revenue is Rs.10.62 lakhs and the annual expenditure is 1.8 lakhs. The net benefit is 8.82 lakhs. Payback period is 2.1 years. This process

The material politics of waste disposal - decentralization and integrated systems

Directory of Open Access Journals (Sweden)

Penelope Harvey

2012-12-01

Full Text Available This article and the previous «Convergence and divergence between the local and regional state around solid waste management. An unresolved problem in the Sacred Valley» from Teresa Tupayachi are published as complementary accounts on the management of solid waste in the Vilcanota Valley in Cusco. Penelope Harvey and Teresa Tupayachi worked together on this theme. The present article explores how discontinuities across diverse instances of the state are experienced and understood. Drawing from an ethnographic study of the Vilcanota Valley in Cusco, the article looks at the material politics of waste disposal in neoliberal times. Faced with the problem of how to dispose of solid waste, people from Cusco experience a lack of institutional responsibility and call for a stronger state presence. The article describes the efforts by technical experts to design integrated waste management systems that maximise the potential for re-cycling, minimise toxic contamination, and turn ‘rubbish’ into the altogether more economically lively category of ‘solid waste’. However while the financialization of waste might appear to offer an indisputable public good, efforts to instigate a viable waste disposal business in a decentralizing political space elicit deep social tensions and contradictions. The social discontinuities that decentralization supports disrupt ambitions for integrated solutions as local actors resist top-down models and look not just for alternative solutions, but alternative ways of framing the problem of urban waste, and by extension their relationship to the state.

Characterization of geopolymer fly-ash based foams obtained with the addition of Al powder or H{sub 2}O{sub 2} as foaming agents

Energy Technology Data Exchange (ETDEWEB)

Ducman, V., E-mail: vilma.ducman@zag.si; Korat, L.

2016-03-15

Recent innovations in geopolymer technology have led to the development of various different types of geopolymeric products, including highly porous geopolymer-based foams, which are formed by the addition of foaming agents to a geopolymer fly-ash based matrix. These agents decompose, or react with the liquid matrix or oxygen in the matrix, resulting in the release of gases which form pores prior to the hardening of the gel. The hardened structure has good mechanical and thermal properties, and can therefore be used for applications in acoustic panels and in lightweight pre-fabricated components for thermal insulation purposes. This study presents the results of the pore-forming process in the case when two different foaming agents, i.e. aluminium powder amounting to 0.07, 0.13 and 0.20 mass. % and H{sub 2}O{sub 2} amounting to 0.5, 1.0, 1.5 and 2.0 mass. %, were added to a fly-ash geopolymer matrix. The physical, mechanical, and microstructural properties of the thus obtained foams, and the effects of the type and amount of the added foaming agent, are presented and discussed. Highly porous structures were obtained in the case of both of the investigated foaming agents, with overall porosities up to 59% when aluminium powder was added, and of up 48% when H{sub 2}O{sub 2} was added. In the latter case, when 2% of the H{sub 2}O{sub 2} foaming agent was added, finer pores (with diameters up to 500 μm) occurred in the structure, whereas somewhat larger pores (some had diameters greater than 1 mm) occurred when the same amount of aluminium powder was added. The mechanical properties of the investigated foams depended on their porosity. In the case of highly porous structures a compressive strength of 3.3 MPa was nevertheless achieved for the samples containing 0.2% of aluminium powder, and 3.7 MPa for those containing 2.0% of H{sub 2}O{sub 2}. - Highlights: • Preparation of geopolymer foams based on fly ash with the addition of Al powder or H{sub 2}O{sub 2} as

LLW disposal, 1996 and beyond, an industry perspective

International Nuclear Information System (INIS)

Genoa, P.H.

1996-01-01

In this article the author reviews what has been done in the past 15 years in terms of opening sites for disposal of low-level radioactive wastes, and what seems to be on the horizon. He reviews process timelines, timelines from regional efforts, and timelines for LLW facilities. The author also looks at what types of changes have been made in the generation, control, and volume of LLW. He examines the pressures which have driven these changes, both from society and from cost control economics. The author tries to look at what government, waste generators, and the waste management industry should do to make progress toward adequate solutions to address the LLW disposal problems

Nuclear Waste Disposal in Space: BEP's Best Hope?

International Nuclear Information System (INIS)

Coopersmith, Jonathan

2006-01-01

The best technology is worthless if it cannot find a market Beam energy propulsion (BEP) is a very promising technology, but faces major competition from less capable but fully developed conventional rockets. Rockets can easily handle projected markets for payloads into space. Without a new, huge demand for launch capability, BEP is unlikely to gain the resources it needs for development and application. Launching tens of thousands of tons of nuclear waste into space for safe and permanent disposal will provide that necessary demand while solving a major problem on earth. Several options exist to dispose of nuclear waste, including solar orbit, lunar orbit, soft lunar landing, launching outside the solar system, and launching into the sun

Inter- and transdisciplinarity as a precondition for final nuclear waste disposal; Inter- und Transdisziplinaritaet als Voraussetzung bei der Entsorgung radioaktiver Reststoffe

Energy Technology Data Exchange (ETDEWEB)

Chaudry, Saleem; Kuppler, Sophie; Smeddinck, Ulrich [Technische Univ. Braunschweig (Germany). Inst. fuer Rechtswissenschaften

2016-03-15

Searching for solutions for solving environmental problems, dissolves the boundaries between the several scientific disciplines. The disposal of radioactive waste requires such interdisciplinary solutions. A problem is described, which generates new problems, if one is solved. The interdisciplinary cooperation for the evaluation of a disposal solution is described. The point of view is a theoretical approach and a transdisciplinary combination of science and the public.

Radioactive waste disposal and public acceptance aspects

Energy Technology Data Exchange (ETDEWEB)

Ulhoa, Barbara M.A.; Aleixo, Bruna L.; Mourao, Rogerio P.; Ferreira, Vinicius V.M., E-mail: mouraor@cdtn.b, E-mail: vvmf@cdtn.b [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

2011-07-01

Part of the public opinion around the world considers the wastes generated due to nuclear applications as the biggest environmental problem of the present time. The development of a solution that satisfies everybody is a great challenge, in that obtaining public acceptance for nuclear enterprises is much more challenging than solving the technical issues involved. Considering that the offering of a final solution that closes the radioactive waste cycle has a potentially positive impact on public opinion, the objective of this work is to evaluate the amount of the radioactive waste volume disposed in a five-year period in several countries and gauge the public opinion regarding nuclear energy. The results show that the volume of disposed radioactive waste increased, a fact that stresses the importance of promoting discussions about repositories and public acceptance. (author)

Radioactive waste disposal and public acceptance aspects

International Nuclear Information System (INIS)

Ulhoa, Barbara M.A.; Aleixo, Bruna L.; Mourao, Rogerio P.; Ferreira, Vinicius V.M.

2011-01-01

Part of the public opinion around the world considers the wastes generated due to nuclear applications as the biggest environmental problem of the present time. The development of a solution that satisfies everybody is a great challenge, in that obtaining public acceptance for nuclear enterprises is much more challenging than solving the technical issues involved. Considering that the offering of a final solution that closes the radioactive waste cycle has a potentially positive impact on public opinion, the objective of this work is to evaluate the amount of the radioactive waste volume disposed in a five-year period in several countries and gauge the public opinion regarding nuclear energy. The results show that the volume of disposed radioactive waste increased, a fact that stresses the importance of promoting discussions about repositories and public acceptance. (author)

Salt disposal: Paradox Basin, Utah

International Nuclear Information System (INIS)

1983-04-01

This report presents the findings of a study conducted for the National Waste Terminal Storage (NWTS) Program. Permanent disposal options are examined for salt resulting from the excavation of a waste repository in the bedded salt deposits of the Paradox Basin of southeastern Utah. The study is based on a repository salt backfill compaction of 60% of the original density which leaves a total of 8 million tons of 95% pure salt to be disposed of over a 30-year period. The feasibility, impacts, and mitigation methods are examined for five options: commercial disposal, permanent onsite surface disposal, permanent offsite disposal, deepwell injection, and ocean and Great Salt Lake disposal. The study concludes the following: Commercial marketing of all repository salt would require a subsidy for transportation to major salt markets. Permanent onsite surface storage is both economically and technically feasible. Permanent offsite disposal is technically feasible but would incur additional transportation costs. Selection of an offsite location would provide a means of mitigating impacts associated with surface storage at the repository site. Deepwell injection is an attractive disposal method; however, the large water requirement, high cost of development, and poor performance of similar operating brine disposal wells eliminates this option from consideration as the primary means of disposal for the Paradox Basin. Ocean disposal is expensive because of high transportation cost. Also, regulatory approval is unlikely. Ocean disposal should be eliminated from further consideration in the Paradox Basin. Great Salt Lake disposal appears to be technically feasible. Great Salt Lake disposal would require state approval and would incur substantial costs for salt transportation. Permanent onsite disposal is the least expensive method for disposal of all repository salt

Buried for ever. The US experience of radioactive waste disposal

International Nuclear Information System (INIS)

Resnikoff, Marvin.

1987-01-01

The United States is the largest producer of radioactive wastes and has considerable experience, not all good, of shallow disposal methods for low level wastes. Indeed, as a result of leakage and contamination, three sites have been closed down and there is concern over another site, at Barnwell in South Carolina. This chapter analyses the geological and technical problems of each of the sites from the viewpoint of the environmental pressure group, the Sienna Club. The sites are at Maxey Flats, Kentucky; Sheffield, Illinois; West Valley, New York; Barnwell; Richland, Washington and Beatly, Nevada. The problems have been those situated in the humid, northern regions where there has been excessive ground water, degradation of waste containers, subsidence and erosion, the presence of chelating agents and a lack of stabilisation and funding for long-term care. In the semi-arid western sites the problems are fewer. However, the cost of transporting the waste to them is high. It is suggested that some of the low-level wastes should be reclassified as high-level wastes and should be disposed of deep underground. (UK)

Proposal of a SiC disposal canister for very deep borehole disposal

Energy Technology Data Exchange (ETDEWEB)

Choi, Heui-Joo; Lee, Minsoo; Lee, Jong-Youl; Kim, Kyungsu [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2016-10-15

In this paper authors proposed a silicon carbide, SiC, disposal canister for the DBD concept in Korea. A. Kerber et al. first proposed the SiC canister for a geological disposal of HLW, CANDU or HTR spent nuclear fuels. SiC has some drawbacks in welding or manufacturing a large canister. Thus, we designed a double layered disposal canister consisting of a stainless steel outer layer and a SiC inner layer. KAERI has been interested in developing a very deep borehole disposal (DBD) of HLW generated from pyroprocessing of PWR spent nuclear fuel and supported the relevant R and D with very limited its own budget. KAERI team reviewed the DBD concept proposed by Sandia National Laboratories (SNL) and developed its own concept. The SNL concept was based on the steel disposal canister. The authors developed a new technology called cold spray coating method to manufacture a copper-cast iron disposal canister for a geological disposal of high level waste in Korea. With this method, 8 mm thin copper canister with 400 mm in diameter and 1200 mm in height was made. In general, they do not give any credit on the lifetime of a disposal canister in DBD concept unlike the geological disposal. In such case, the expensive copper canister should be replaced with another one. We designed a disposal canister using SiC for DBD. According to an experience in manufacturing a small size canister, the fabrication of a large-size one is a challenge. Also, welding of SiC canister is not easy. Several pathways are being paved to overcome it.

Research on geological disposal: R and D concept on geological disposal

International Nuclear Information System (INIS)

1993-01-01

The objective on geological disposal of high-level radioactive wastes are to ensure the long term radiological protection of the human and his environment in accordance with current internationally agreed radiation protection principles. The principle of geological disposal is to settle the high-level wastes in deep underground so as to isolate them from the human and his environment considering the existence of groundwater. Japan is currently in the stage of assessing technical feasibility of geological disposal to the extent practicable. In accordance with the AEC (Atomic Energy Commission) policy in 1989, PNC (Power Reactor and Nuclear Fuel Development Corporation) has conducted the research and development on geological disposal in three areas: 1) studies of geological environment, 2) research and development of disposal technology, and 3) performance assessment study. (author)

Curriculum and instruction in nuclear waste disposal

International Nuclear Information System (INIS)

Robinson, M.; Lugaski, T.; Pankratius, B.

1991-01-01

Curriculum and instruction in nuclear waste disposal is part of the larger problem of curriculum and instruction in science. At a time when science and technological literacy is crucial to the nation's economic future fewer students are electing to take needed courses in science that might promote such literacy. The problem is directly related to what science teachers teach and how they teach it. Science content that is more relevant and interesting to students must be a part of the curriculum. Science instruction must allow students to be actively involved in investigating or playing the game of science

Criteria for long-term hazard assessment of chemotoxic and radiotoxic waste disposal

International Nuclear Information System (INIS)

Merz, E.R.

1988-01-01

Present-day human activities generate chemotoxic as well as radiotoxic wastes. They must likewise be considered as extremely hazardous. If wastes are composed simultaneously of both kinds, as may occur in nuclear facility operations or nuclear medical applications, the material is called mixed waste. Whereas radioactive waste management and disposal have received considerable attention in the past, less care has been devoted to chemotoxic wastes. Also, mixed wastes may pose problems diverging from singly composed materials. The disposal of mixed wastes is not sufficiently well regulated in the Federal Republic of Germany. Currently, non-radioactive hazardous wastes are mostly disposed of by shallow land burial. Much more rigorous safety precautions are applied with regard to radioactive wastes. According to the orders of the German Federal Government, their disposal is only permitted in continental underground repositories. These repository requirements for radioactive waste disposal should be superior to the near-surface disposal facilities. At present, federal and state legislation do not permit hazardous chemical and radioactive wastes to be deposited simultaneously. It is doubtful whether this instruction is always suitable and also justified. This paper presents a modified strategy

Organizing and managing radioactive waste disposal as an experiment

International Nuclear Information System (INIS)

Cook, B.J.; Emel, J.L.; Kasperson, R.E.

1990-01-01

This paper examines organization and management issues engendered by the national program for permanent disposal of commercial radioactive wastes. The description of current organizational and managerial responses to the waste disposal problem serves as a springboard for consideration of the technical, political, and organizational constraints that impinge upon the waste-management effort. Taking these constraints into account, the authors apply ideas that have emerged from previous radioactive waste-management studies and research on organizations, concluding that a change of course is needed. As an alternative, they propose an experimental approach predicated on the waste-management organization's acknowledging uncertainty and constructing responses that seek to reduce uncertainty systematically and without distortion

Disposal of high level nuclear wastes: thermodynamic equilibrium and environment ethics

International Nuclear Information System (INIS)

Rana, M.A.

2009-01-01

Contamination of soil, water or air, due to a failure of containment or disposal of high level nuclear wastes, can potentially cause serious hazards to the environment or human health. Essential elements of the environment and radioactivity dangers to it are illustrated. Issues of high level nuclear waste disposal are discussed with a focus on thermodynamic equilibrium and environment ethics. Major aspects of the issues are analyzed and described briefly to build a perception of risks involved and ethical implications. Nuclear waste containment repository should be as close as possible to thermodynamic equilibrium. A clear demonstration about safety aspects of nuclear waste management is required in gaining public and political confidence in any possible scheme of permanent disposal. Disposal of high level nuclear waste offers a spectrum of environment connected challenges and a long term future of nuclear power depends on the environment friendly solution of the problem of nuclear wastes. (authors)

History of geological disposal concept (3). Implementation phase of geological disposal (2000 upward)

International Nuclear Information System (INIS)

Masuda, Sumio; Sakuma, Hideki; Umeki, Hiroyuki

2015-01-01

Important standards and concept about geological disposal have been arranged as an international common base and are being generalized. The authors overview the concept of geological disposal, and would like this paper to help arouse broad discussions for promoting the implementation plan of geological disposal projects in the future. In recent years, the scientific and technological rationality of geological disposal has been recognized internationally. With the addition of discussions from social viewpoints such as ethics, economy, etc., geological disposal projects are in the stage of starting after establishment of social consensus. As an international common base, the following consolidated and systematized items have been presented as indispensable elements in promoting business projects: (1) step-by-step approach, (2) safety case, (3) reversibility and recovery potential, and (4) trust building and communications. This paper outlines the contents of the following cases, where international common base was reflected on the geological disposal projects in Japan: (1) final disposal method and safety regulations, and (2) impact of the Great East Japan Earthquake and Fukushima Daiichi Nuclear Power Station accident on geological disposal plan. (A.O.)

Democratic input into the nuclear waste disposal problem: The influence of geographical data on decision making examined through a Web-based GIS

Science.gov (United States)

Evans, Andrew J.; Kingston, Richard; Carver, Steve

This paper elucidates the manner in which users of an online decision support system respond to spatially distributed data when assessing the solution to environmental risks, specifically, nuclear waste disposal. It presents tests for revealing whether users are responding to geographical data and whether they are influenced by their home location (Not in My Back Yard - style behavior). The tests specifically cope with problems associated with testing home-to-risk distances where both locations are constrained by the shape of the landmass available. In addition, we detail the users' wider feelings towards such a system, and reflect upon the possibilities such systems offer for participatory democracy initiatives.

Disposal and re-use of TENORM - legal limitations and obstacles

International Nuclear Information System (INIS)

Weiss, D.; Ettenhuber, E.

2004-01-01

While implementing EURATOM guideline 96/29 in the German legislation, in June of 2001 an essential pre-condition was created for re-use or disposal of TENORM. An essential progress has been achieved allowing to re-use TENORM or to dump it together with other residues and waste, if the specific activity does not exceed the limits defined in the radiation protection ordinance (StrlSchV). Otherwise, if the specified limits in terms of concentration or radiation dose are exceeded, than these materials must remain under radiological protection. A practical application of the new German regulation turns out to be difficult especially for disposal together with other waste and for re-use as backfilling material in mines taking into account problems arising from adaptation of the respective legislation on radiation protection, soil protection, waste management and shipment of dangerous goods. The report tackles obstacles for re-use and disposal of TENORM together with garbage and toxic waste arising from the new legislation. Otherwise, proposals will be given how obstacles of selected options for re-use and disposal can be overcome. (orig.)

DISPOSAL OF LOW AND INTERMEDIATE LEVEL WASTE IN HUNGARY

Directory of Open Access Journals (Sweden)

Bálint Nős

2012-07-01

Full Text Available There are two operating facilities for management of low and intermediate level radioactive waste in Hungary. Experience with radioactive waste has a relatively long history and from its legacy some problems are to be solved, like the question of the historical waste in the Radioactive Waste Treatment and Disposal Facility (RWTDF. Beside the legacy problems the current waste arising from the Nuclear Power Plant (NPP has to be dealt with a safe and economically optimized way.

Radioactivity: ''small users, big problems''

International Nuclear Information System (INIS)

McDonnell, C.

1993-01-01

In the United Kingdom there are at least one thousand small users of radioactivity in industry, in medicine, in higher education establishments and even schools. These users of small amounts of radioactivity, covering a wide variety of forms and applications, have difficulty in disposing of their wastes. Disposal provisions for users outside the nuclear industry, the practical problems they encounter and the future developments likely are discussed. (UK)

Radioactive waste disposal and study of mineral deposit of uranium

International Nuclear Information System (INIS)

Doi, Kazumi

2003-01-01

To realize high level radioactive waste disposal, it is need to guarantee with high reliability safety of isolation of radioactive waste during some ten thousand years. There are two important factors related to geophysics such as ground water and diastrophism. The problems to be solved in the present point are followings; 1) increasing data of characteristics of radionuclide within high level radioactive waste, 2) development of undisruptive exploration technologies of lithosphere, especially formal fabric of pore and 3) improvement of protection technologies of diastrophism. Our country has to make efforts to realize the safety of isolation of radioactive waste on the basis of researches, by means of keeping them in the strong facilities without disposal. The formation of concentrated uranium in the mineral deposit was explained in relation with high level radioactive waste disposal. (S.Y.)

Progress on developing expert systems in waste management and disposal

International Nuclear Information System (INIS)

Rivera, A.L.; Ferrada, J.J.

1990-01-01

The concept of artificial intelligence (AI) represents a challenging opportunity in expanding the potential benefits from computer technology in waste management and disposal. The potential of this concept lies in facilitating the development of intelligent computer systems to help analysts, decision makers, and operators in waste and technology problem solving similar to the way that machines support the laborer. Because the knowledge of multiple human experts is an essential input in the many aspects of waste management and disposal, there are numerous opportunities for the development of expert systems using software products from AI. This paper presents systems analysis as an attractive framework for the development of intelligent computer systems of significance to waste management and disposal, and it provides an overview of limited prototype systems and the commercially available software used during prototype development activities

Information on commercial disposal facilities that may have received offshore drilling wastes.

Energy Technology Data Exchange (ETDEWEB)

Gasper, J. R.; Veil, J. A.; Ayers, R. C., Jr.

2000-08-25

The U.S. Environmental Protection Agency (EPA) is developing regulations that would establish requirements for discharging synthetic-based drill cuttings from offshore wells into the ocean. Justification for allowing discharges of these cuttings is that the environmental impacts from discharging drilling wastes into the ocean may be less harmful than the impacts from hauling them to shore for disposal. In the past, some onshore commercial facilities that disposed of these cuttings were improperly managed and operated and left behind environmental problems. This report provides background information on commercial waste disposal facilities in Texas, Louisiana, California, and Alaska that received or may have received offshore drilling wastes in the past and are now undergoing cleanup.

Ocean Disposal Site Monitoring

Science.gov (United States)

EPA is responsible for managing all designated ocean disposal sites. Surveys are conducted to identify appropriate locations for ocean disposal sites and to monitor the impacts of regulated dumping at the disposal sites.

Nuclear energy's dilemma: disposing of hazardous radioactive waste safely. Report to the congress

International Nuclear Information System (INIS)

1977-01-01

The unsolved problem of radioactive waste disposal threatens the future of nuclear power in the United States. Nuclear critics, the public, business leaders, and Government officials concur that a solution to the disposal problem is critical to the continued growth of nuclear energy. The Energy Research and Development Administration has begun a program to demonstrate by the mid-1980s the feasibility and safety of placing radioactive wastes in deep geological formations. GAO points out that not only has progress been negligible to date, but that future program goals are overly optimistic because the Energy Research and Development Administration faces many unsolved social, regulatory, and geological obstacles. GAO also discusses the progress and problems the Energy Research and Development Administration faces in managing its radioactive waste and how the Nuclear Regulatory Commission is handling the problem of large amounts of spent nuclear fuel now accumulating at nuclear power plants, and makes a number of recommendations for regulatory and program management changes

Geological disposal of radioactive wastes

International Nuclear Information System (INIS)

Sato, Tsutomu

2000-01-01

For disposing method of radioactive wastes, various feasibilities are investigated at every nations and international organizations using atomic energy, various methods such as disposal to cosmic space, disposal to ice sheet at the South Pole and so forth, disposal into ocean bed or its sediments, and disposal into ground have been examined. It is, however, impossible institutionally at present, to have large risk on accident in the disposal to cosmic space, to be prohibited by the South Pole Treaty on the disposal to ice sheet at the South Pole, and to be prohibited by the treaty on prevention of oceanic pollution due to the disposal of wastes and so forth on the disposal into oceanic bed or its sediments (London Treaty). Against them, the ground disposal is thought to be the most powerful method internationally from some reasons shown as follows: no burden to the next generation because of no need in long-term management by human beings; safety based on scientific forecasting; disposal in own nation; application of accumulated technologies on present mining industries, civil engineering, and so forth to construction of a disposal facility; and, possibility to take out wastes again, if required. For the ground disposal, wastes must be buried into the ground and evaluated their safety for long terms. It is a big subject to be taken initiative by engineers on geoscience who have quantified some phenomena in the ground and at ultra long term. (G.K.)

The disposal of radioactive solvent waste

International Nuclear Information System (INIS)

Dean, B.; Baker, W.T.

1976-01-01

As the use of radioisotope techniques increases, laboratories are faced with the problem of disposing of considerable quantities of organic solvent and aqueous liquid wastes. Incineration or collection by a waste contractor both raise problems. Since most of the radiochemicals are preferentially water soluble, an apparatus for washing the radiochemicals out into water and discharging into the normal drainage system in a high diluted form is described. Despite the disadvantages (low efficiency, high water usuage, loss of solvent in presence of surface active agents, precipitation of phosphors from dioxan based liquids) it is felt that the method has some merit if a suitably improved apparatus can be designed at reasonable cost. (U.K.)

Disposal of Radioactive Waste

International Nuclear Information System (INIS)

2011-01-01

This Safety Requirements publication applies to the disposal of radioactive waste of all types by means of emplacement in designed disposal facilities, subject to the necessary limitations and controls being placed on the disposal of the waste and on the development, operation and closure of facilities. The classification of radioactive waste is discussed. This Safety Requirements publication establishes requirements to provide assurance of the radiation safety of the disposal of radioactive waste, in the operation of a disposal facility and especially after its closure. The fundamental safety objective is to protect people and the environment from harmful effects of ionizing radiation. This is achieved by setting requirements on the site selection and evaluation and design of a disposal facility, and on its construction, operation and closure, including organizational and regulatory requirements.

Present state on research and development of underground disposal

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-12-01

In September, 1996, Power Reactor and Nuclear Fuel Development Corp. (PNC) arranged her old research and development (R and D) results to issue as a shape of `Technical report on R and D of high level radioactive waste underground disposal`. On the other hand, Radioactive waste special party in Committee of Atomic Energy at that time evaluated that technical possibility for safety establishment of underground disposal in Japan was elucidated and showed future problems in the technical development. Therefore, PNC proceeded further R and D for the second arrangement under consideration of such comments. As a result, in investigation of geological environment condition, main points were laid at study on rear-field feature and its long-term stability. In development of disposal technique, main points were laid at elucidation of design requirements confirmable to the near-field evaluation, main points were laid at upgrading validity of evaluation model to analytically evaluate the near-field feature using data with high reliability. (G.K.)

Present state on research and development of underground disposal

International Nuclear Information System (INIS)

1996-12-01

In September, 1996, Power Reactor and Nuclear Fuel Development Corp. (PNC) arranged her old research and development (R and D) results to issue as a shape of 'Technical report on R and D of high level radioactive waste underground disposal'. On the other hand, Radioactive waste special party in Committee of Atomic Energy at that time evaluated that technical possibility for safety establishment of underground disposal in Japan was elucidated and showed future problems in the technical development. Therefore, PNC proceeded further R and D for the second arrangement under consideration of such comments. As a result, in investigation of geological environment condition, main points were laid at study on rear-field feature and its long-term stability. In development of disposal technique, main points were laid at elucidation of design requirements confirmable to the near-field evaluation, main points were laid at upgrading validity of evaluation model to analytically evaluate the near-field feature using data with high reliability. (G.K.)

Solid Waste Disposal in Chinese Cities: An Evaluation of Local Performance

Directory of Open Access Journals (Sweden)

Boya Zhou

2017-12-01

Full Text Available China meets increasingly serious solid waste problems and has adopted various policies in response in recent years. Meanwhile, few studies have investigated the performance of solid waste disposal through statistical analysis with empirical data. This study examines provincial resource use policy’s influence on the comprehensive utilization rate of industrial solid waste in Chinese cities. Through comparing results for statistical analysis in the year 2009 and 2015 by multiple linear regression analysis, this study analyzes similarities and differences in the drivers for solid waste disposal in the era of the 11th Five-Year Plan and the 12th Five-Year Plan in China. It finds that the adoption of resource use policy positively increases the comprehensive utilization rate of industrial solid waste. Other factors such as industrial SO2 emission, local environmental regulations, GDP per capita, population density and educational level also affect industrial solid waste disposal. Therefore, China should continue implementing solid waste disposal policies, upgrade current industrial systems, push forward economic and social reform and increase environmental education to enhance the effectiveness of solid waste disposal for long-term sustainable development.

Regional waste treatment with monolith disposal for low-level radioactive waste

International Nuclear Information System (INIS)

Forsberg, C.W.

1983-01-01

An alternative system is proposed for the disposal of low-level radioactive waste. This system, called REgional Treatment with MOnolith Disposal (RETMOD), is based on integrating three commercial technologies: automated package warehousing, whole-barrel rotary kiln incineration, and cement-based grouts for radioactive waste disposal. In the simplified flowsheet, all the sludges, liquids, resins, and combustible wastes are transported to regional facilities where they are incinerated. The ash is then mixed with special cement-based grouts, and the resulting mixture is poured into trenches to form large waste-cement monoliths. Wastes that do not require treatment, such as damaged and discarded equipment, are prepositioned in the trenches with the waste-cement mixture poured on top. The RETMOD system may provide higher safety margins by conversion of wastes into a solidified low-leach form, creation of low-surface area waste-cement monoliths, and centralization of waste processing into a few specialized facilities. Institutional problems would be simplified by placing total responsibility for safe disposal on the disposal site operator. Lower costs may be realized through reduced handling costs, the economics of scale, simplified operations, and less restrictive waste packaging requirements

A top priority problem of national radiation protection - proper disposal of research reactor spent fuel

International Nuclear Information System (INIS)

Marinkovic, N.; Matausek, M.V.; Jovic, V.

1997-01-01

The paper presents basic facts about RA research reactor at the Vinca Institute. The present state of the RA reactor spent fuel storage pool appears to be a serious safety and radiological problem, which must be solved urgently, independent of the decision about the future status of the reactor itself. The following paragraphs describe current activities on improving storage conditions of the research reactor RA spent fuel. Activities performed so far, concerning identification and improvement of the spent fuel storage conditions are presented. These are verification of radiation protection measures, radiological and chemical analyses, visual inspection and photographing, safety analyses and nuclear criticality studies.A project for long-term solution of the research reactor spent fuel storage is proposed. In order to minimise further corrosion and establish strict control of all the relevant technological parameters of the utility, improvement of conditions for disposal of the fuel in the existing storage, is foreseen in the first phase. New dry storage for long-term storing of the spent fuel should be built during the second phase of the project. Particular attention is paid to the activities related to radiation protection and waste treatment, starting from standard monitoring and control, radiological analyses, regulations and legislation, to complicated handling of high level radioactive waste. (authors)

Reversibility and switching options values in the geological disposal of radioactive waste

International Nuclear Information System (INIS)

Ionescu, Oana; Spaeter, Sandrine

2011-07-01

This article offers some economic insights for the debate on the reversible geological disposal of radioactive waste. Irreversibility due to large sunk costs, an important degree of flexibility and several sources of uncertainty are taken into account in the decision process relative to the radioactive waste disposal. We draw up a stochastic model in a continuous time framework to study the decision problem of a reversible repository project for the radioactive waste, with multiple disposal stages. We consider that the value of reversibility, related to the radioactive waste packages, is jointly affected by economic and technological uncertainty. These uncertainties are modeled, first, by a 2-Dimensional Geometric Brownian Motion, and, second, by a Geometric Brownian Motion with a Poisson jump process. A numerical analysis and a sensitivity study of various parameters are also proposed. Switching options values in the geological disposal of radioactive waste. (authors)

Development of an integrated software system (Digital Geological Disposal System) for design and evaluation of HLW disposal system

International Nuclear Information System (INIS)

Fusaeda, Shigeki; Yanagisawa, Ichiro; Imamura, Naoko

2000-02-01

In this study, a design study on 'Digital Geological Disposal System' has been carried out in order to define the developmental goal for the first phase (-FY2002) system and to demonstrate the feasibility of the system development. The key conclusions are summarized as follows: (1) As the result of the basic design of the Integrated Analysis Platform (IAP), the representation method for the procedure of analysis that is called analysis network, the configuration of the object that makes up the analysis network, and the execution control mechanism of the analysis network are newly proposed in order to enhance the flexibility of IAP. (2) A prototyping study concerning an optimization problem that includes cavity stability analysis and thermal analysis, showed that the design of IAP is practical one and also has enough flexibility to solve complex problems expected in the repository design processes. (3) The development plan for the 'Digital Geological Disposal System' has been investigated based on the discussions about the system usage by the potential users such as the regulators, the implementation body and the research institutes, as well as the technical discussions. As a result, short-term (for the first phase) and long-term development plans have been proposed. (author)

ENTRIA 2014. Memorandum on the disposal of high-level radioactive residuals; ENTRIA 2014. Memorandum zur Entsorgung hochradioaktiver Reststoffe

Energy Technology Data Exchange (ETDEWEB)

Roehlig, Klaus-Juergen; Walther, Clemens; Bach, Friedrich-Wilhelm [Niedersaechsische Technische Hochschule, Braunschweig, Clausthal-Zellerfeld, Hannover (Germany); and others

2014-04-30

The memorandum on the disposal of high-level radioactive residuals covers the following issues: description of the problem: a ''wicked problem'', risks and NIMBY, the site selection law, international boundary conditions; disposal strategy and types of facilities: safety and reversibility, long-term surface storage, deep storage; risk and safety; procedural justice and the site selection process; social innovations and the requirement of long-term institutions; conclusion - central stress fields.

Geographic factors related to site suitability of low-level waste disposal

Science.gov (United States)

Zittel, H. E.

Factors related to the site suitability of low level waste disposal sites are discussed including those which might be considered environmental and those dealing with site criteria. Possible population criteria, alternative site selection, transportation criteria, and community involvement are considered. All these factors are based on the premise that the technology exists to carry out low level waste disposal in a manner such that public health and safety can be insured. It is concluded that problems encountered in siting low level waste facilities are largely societal and political in nature.

Analysis of heat and mass transfer in sub-seabed disposal of nuclear waste

International Nuclear Information System (INIS)

Hickox, C.E.; Gartling, D.K.; McVey, D.F.; Russo, A.J.; Nuttall, H.E.

1980-01-01

A mathematical basis is developed for the prediction of thermal and radionuclide transport in marine sediments. The theory is applied to the study of radioactive waste disposal by emplacement, in specially designed containers, well below the sediment/water interface. Numerical results are obtained for a specified model problem through use of two computer programs designed primarily for the analysis of waste disposal problems. One program (MARIAH) provides descriptions of the temperature and velocity fields induced by the presence of a container of thermally active nuclear waste. A second program (IONMIG), which utilizes the results of the thermal analysis, is used to provide predictions for the migration of four representative radionuclides: 239 Pu, 137 Cs, 129 I, and 99 Tc

Safety indicators for the safety assessment of radioactive waste disposal. Sixth report of the Working Group on Principles and Criteria for Radioactive Waste Disposal

International Nuclear Information System (INIS)

2003-09-01

The report describes a few indicators that are considered to be the most promising for assessing the long term safety of disposal systems. The safety indicators that are discussed here may be applicable to a range of disposal systems for different waste types, including near surface disposal facilities for low level waste. The appropriateness of the different indicators may, however, vary depending on the characteristics of the waste, the facility and the assessment context. The focus of the report is thus on the use of time-scales of containment and transport, and radionuclide concentrations and fluxes, as indicators of disposal system safety, that may complement the more usual safety indicators of dose and risk. Summarised are the broad elements that a safety case for an underground radioactive waste disposal facility should possess and the role and use of performance and safety indicators within these elements. An overview of performance and safety indicators is given. The use is discussed of dose and risk as safety indicators and, in particular, problems that can arise in their use. Also presented are some specific indicators that have the potential to be used as complementary safety indicators. Discussed is also how fluxes of naturally occurring elements and radionuclides due to the operation of natural processes such as erosion and groundwater discharge may be quantified for comparison with fluxes of waste derived contaminants

Pulp fiction - The volunteer concept (or how not to site additional LLRW disposal capacity)

International Nuclear Information System (INIS)

Burton, D.A.

1995-01-01

Experiences of compacts and of individual states throughout the nation indicate that low-level radioactive waste disposal siting processes, based from the beginning upon the volunteer concept are fraught with problems. Most apparent among these problems is that the volunteer concept does not lead to scientifically and technically based siting endeavors. Ten years have passed since the Amendments Act of 1985, and no compact or state has been - successful in providing for new LLRW disposal capacity. That failure can be traced in part to the reliance upon the volunteer concept in siting attempts. If success is to be achieved, the future direction for LLRW management must focus on three areas: first, a comprehensive evaluation of all LLRW management options, including reduction of waste generated and on-site storage; secondly, a comprehensive evaluation of the current as well as projected waste stream, to determine the amount of disposal capacity actually needed; and, finally, sound scientifically and technically based siting processes

Pulp fiction - The volunteer concept (or how not to site additional LLRW disposal capacity)

Energy Technology Data Exchange (ETDEWEB)

Burton, D.A. [Heartland Operation to Protect the Environment, Inc., Auburn, NE (United States)

1995-12-31

Experiences of compacts and of individual states throughout the nation indicate that low-level radioactive waste disposal siting processes, based from the beginning upon the volunteer concept are fraught with problems. Most apparent among these problems is that the volunteer concept does not lead to scientifically and technically based siting endeavors. Ten years have passed since the Amendments Act of 1985, and no compact or state has been - successful in providing for new LLRW disposal capacity. That failure can be traced in part to the reliance upon the volunteer concept in siting attempts. If success is to be achieved, the future direction for LLRW management must focus on three areas: first, a comprehensive evaluation of all LLRW management options, including reduction of waste generated and on-site storage; secondly, a comprehensive evaluation of the current as well as projected waste stream, to determine the amount of disposal capacity actually needed; and, finally, sound scientifically and technically based siting processes.

Experience and lessons learned from emergency disposal of Fukushima nuclear power station accident

International Nuclear Information System (INIS)

Xu Xiegu; Zhen Bei; Yang Xiaoming; Chen Xiaohua

2012-01-01

After Fukushima nuclear accident, we visited the related medical aid agencies for nuclear accidents and conducted investigations in disaster-affected areas in Japan. This article summarizes the problems with emergency disposal of Fukushima nuclear accident while disclosing problems should be solved during the emergency force construction for nuclear accidents. (authors)

Study on garbage disposal mode with low energy consumption for villages and towns in cold region

Directory of Open Access Journals (Sweden)

Ma Yi

2016-01-01

Full Text Available Through field research of typical villages and towns in China's northern cold region, this paper research energy consumption and resource recovery in the process of village and town garbage collection and disposal and organizes current situation and problems of village and town garbage collection and disposal. At present, village and town garbage collection and disposal means and thoughts are traditional and lag behind in China's northern cold region. There is the lack of garbage collection and disposal mode suitable for cold villages and towns. Thus, village and town resources are not effectively utilized, and residents’ living environment is affected continuously. This paper selects two mature garbage disposal methods: sanitary landfill and incineration power generation. Meanwhile, energy consumption and ultimate emission utilization of two schemes in garbage collection and disposal links are overall compared to propose garbage collection and disposal mode with low energy consumption suitable for green villages and towns in cold region. Besides, various control indexes of village and town garbage disposal schemes are explained in detail in combination of specific conditions.

Disposal configuration options for future uses of greater confinement disposal at the Nevada Test Site

International Nuclear Information System (INIS)

Price, L.

1994-09-01

The US Department of Energy (DOE) is responsible for disposing of a variety of radioactive and mixed wastes, some of which are considered special-case waste because they do not currently have a clear disposal option. The DOE's Nevada Field Office contracted with Sandia National Laboratories to investigate the possibility of disposing of some of this special-case waste at the Nevada Test Site (NTS). As part of this investigation, a review of a near-surface and subsurface disposal options that was performed to develop alternative disposal configurations for special-case waste disposal at the NTS. The criteria for the review included (1) configurations appropriate for disposal at the NTS; (2) configurations for disposal of waste at least 100 ft below the ground surface; (3) configurations for which equipment and technology currently exist; and (4) configurations that meet the special requirements imposed by the nature of special-case waste. Four options for subsurface disposal of special-case waste are proposed: mined consolidated rock, mined alluvium, deep pits or trenches, and deep boreholes. Six different methods for near-surface disposal are also presented: earth-covered tumuli, above-grade concrete structures, trenches, below-grade concrete structures, shallow boreholes, and hydrofracture. Greater confinement disposal (GCD) in boreholes at least 100 ft deep, similar to that currently practiced at the GCD facility at the Area 5 Radioactive Waste Management Site at the NTS, was retained as the option that met the criteria for the review. Four borehole disposal configurations are proposed with engineered barriers that range from the native alluvium to a combination of gravel and concrete. The configurations identified will be used for system analysis that will be performed to determine the disposal configurations and wastes that may be suitable candidates for disposal of special-case wastes at the NTS

The disposal of radioactive wastes in Brazil with special emphasis on rocks

International Nuclear Information System (INIS)

Enokihara, Cyro Teiti

1983-01-01

The disposal of radioactive wastes in geological formations seems to be the most appropriate solution for the nuclear waste problem. The disposal sites must provide the maximum safety for the radionuclides during its decay period. The study presents a general analysis of three types rocks: salt, granite and basalt. In our analysis we have dealt with the following aspects: geology, tectonics, seismicity, hydrogeology , mineral resources, geomorphology, population and access. The studied regions were: Sergipe-Alagoas and Reconcavo Basins, Northeastern and Southeastern Folded Regions and Parana Basin. Our study contains the macro-analysis needed for the selection of a safe site for radioactive waste disposal. We believe this work will be useful as a first step for further micro-analysis of selected sites. (author)

Biomass gasification: a strategy for energy recovery and disposal of ...

African Journals Online (AJOL)

Biomass gasification: a strategy for energy recovery and disposal of industrial and municipal wastes. Anurag Pandey, Anupam Shukla. Abstract. Energy from biological organic waste as an aspect of sustainable waste management is probably the most contentious. Solid and liquid wastes are a rapidly growing problem ...

New DEA rules expand options for controlled substance disposal.

Science.gov (United States)

Peterson, David M

2015-03-01

Prescription drug abuse and overdose are rapidly growing problems in the United States. The United States federal Disposal of Controlled Substances Rule became effective 9 October 2014, implementing the Secure and Responsible Drug Disposal Act of 2010 (Disposal Act). These regulations target escalating prescription drug misuse by reducing accumulation of unused controlled substances that may be abused, diverted or accidentally ingested. Clinical areas that can now participate in collecting unused controlled substances include retail pharmacies, hospitals or clinics with an onsite pharmacy, and narcotic treatment programs. Collection methods include placing a controlled substance collection receptacle or instituting a mail-back program. Because prompt onsite destruction of collected items is required of mail-back programs, collection receptacles are more likely to be used in clinical areas. Retail pharmacies and hospitals or clinics with an onsite pharmacy may also place and maintain collection receptacles at long-term care facilities. The Act and Rule are intended to increase controlled substance disposal methods and expand local involvement in collection of unused controlled substances. Potential barriers to participating in controlled substance collection include acquisition of suitable collection receptacles and liners, lack of available space meeting the necessary criteria, lack of employee time for verification and inventory requirements, and program costs.

Fire analyses in central and disposal tunnels by APROS; Keskus- ja loppusijoitustunneleiden palotarkasteluja APROSilla

Energy Technology Data Exchange (ETDEWEB)

Peltokorpi, L.; Kukkola, T.; Nieminen, J. [Fortum Power and Heat Oy, Espoo (Finland)

2012-12-15

The central tunnels and the disposal tunnels on the north-east disposal area are the target areas of the fire studies. Target is to maintain under pressure in the fire zone in case of a fire. In the central tunnels a fire of a drilling jumbo with moderate fire propagation is used as heat release rate. In the disposal tunnel the heat release rate of a canister transfer and installation vehicle fire received as a result of the pyrolysis analyze as well as an average heat release rate of a van fire are used. Inlet air is to be conducted to the back end of the fire zone and the exhaust is to be lead out from the beginning of the fire zone. The worst location of the fire is in the beginning of the fire zone just below of the exhaust air clap valve. The size of the fire zone does not have big impact on pressure. In all analyzed cases the fire zone remains too long time over pressurized. Inlet air flow of a 30 m{sup 3}/s is too much. The rotation controlled booster blowers will solve the pressure problems of the fire zone in fire cases. The rotation is controlled by the fire zone pressure. The fire of the canister transfer and installation vehicle in the central tunnel will not cause problems. The disposal tunnel fire door should be kept open, if the canister transfer and installation vehicle or the bentonite blocks transfer and installation vehicle is driven into the disposal tunnel. If a fire is caught in the disposal tunnel then the fire zone in the central tunnel is to be closed and the pressure is controlled by the rotation controlled booster blowers. If a personnel car or a van is driven into the disposal tunnel, then fire door of the disposal is to be kept closed against fires in the central tunnel. (orig.)

Evaluation of Proposed New LLW Disposal Activity: Disposal of Aqueous PUREX Waste Stream in the Saltstone Disposal Facility

International Nuclear Information System (INIS)

Cook, J.R.

2003-01-01

The Aqueous PUREX waste stream from Tanks 33 and 35, which have been blended in Tank 34, has been identified for possible processing through the Saltstone Processing Facility for disposal in the Saltstone Disposal Facility

Summary review of rock mechanics workshop on radioactive waste disposal

International Nuclear Information System (INIS)

Carter, N.L.; Goodman, R.E.; Merrill, R.H.

1977-01-01

Presentations, critiques and recommendations for the disposal of commercial radioactive waste based upon an analysis of the information presented at the Rock Mechanics Review/Workshop, Denver, Colorado, December 16-17, 1976 are summarized. The workshop, comprised of both formal and informal sessions, with about 50 participants, was hosted by RE/SPEC Inc. and Dr. Paul F. Gnirk, President and was sponsored by the Office of Waste Isolation (OWI), led by Dr. William C. McClain. The panel of reviewers, responsible for this report, consisted of Neville L. Carter, Richard E. Goodman, and Robert H. Merrill. These panel members were selected not only on the basis of their experience in various aspects of Rock Mechanics and Mining Engineering but also because they have had no previous active participation in problems concerning disposal of radioactive waste. By way of a general comment, the review panel was very favorably impressed with the Rock Mechanics research efforts, supported by OWI, on this problem and with the level of technical competence of those carrying out the research. Despite the rather preliminary nature of the results presented and the youth of the program itself, it is clear that the essential ingredients for a successful program are at hand, especially as regards disposal in natural salt formations. These include laboratory studies of appropriate rock deformation, numerical analyses of thermal and mechanical stresses around openings, and in situ field tests. We shall comment on each of these three major areas in turn. We shall then offer recommendations for their improvement, and, finally, we shall make more general recommendations for future considerations of the OWI radioactive waste disposal program

The treatment and packaging of waste plutonium and waste actinides for disposal

International Nuclear Information System (INIS)

Taylor, R.F.

1988-07-01

The objectives of this work have been to review the current state of knowledge on the treatment and packaging of unusable or surplus plutonium and other waste actinides for disposal and to identify any gaps in data essential for the development of a preferred route. The exercise was based on published data which said the quantity currently to be disposed of was 50 tonnes in oxide form. A literature review over the period 1978 to 1988 was carried out and a computerised database specific to the exercise was created. From this it is concluded that there are no insuperable problems to the formulation of a disposal route although there is none currently proven. The preferred wasteform would be a glass or synthetic rock. The major complication lies in the fissile nature of plutonium which dictates limits to the package size and places restrictions on the production and disposal routes. Additional work necessary to permit a final decision is listed. (author)

Radioactive waste problems in Russia

International Nuclear Information System (INIS)

Bridges, O.; Bridges, J.W.

1995-01-01

The collapse of the former Soviet Union, with the consequent shift to a market driven economy and demilitarisation, has had a profound effect on the nuclear and associated industries. The introduction of tighter legislation to control the disposal of radioactive wastes has been delayed and the power and willingness of the various government bodies responsible for its regulation is in doubt. Previously secret information is becoming more accessible and it is apparent that substantial areas of Russian land and surface waters are contaminated with radioactive material. The main sources of radioactive pollution in Russia are similar to those in many western countries. The existing atomic power stations already face problems in the storage and safe disposal of their wastes. These arise because of limited on site capacity for storage and the paucity of waste processing facilities. Many Russian military nuclear facilities also have had a sequence of problems with their radioactive wastes. Attempts to ameliorate the impacts of discharges to important water sources have had variable success. Some of the procedures used have been technically unsound. The Russian navy has traditionally dealt with virtually all of its radioactive wastes by disposal to sea. Many areas of the Barents, Kola and the Sea of Japan are heavily contaminated. To deal with radioactive wastes 34 large and 257 small disposal sites are available. However, the controls at these sites are often inadequate and illegal dumps of radioactive waste abound. Substantial funding will be required to introduce the necessary technologies to achieve acceptable standards for the storage and disposal of radioactive wastes in Russia. (author)

Problematic Incinerator Ash: A Case Study of Finding a Successful Treatment Approach

International Nuclear Information System (INIS)

Gering, K. L.

1999-01-01

The Idaho National Engineering and Environmental Laboratory (INEEL) produces incinerator flyash and bottom ash as a consequence of burning low-level radioactive waste materials at the Waste Experimental Reduction Facility (WERF). The incineration process greatly reduces original waste volumes but concentrates the metals that are present, such as toxic metals (most notably cadmium, lead, and antimony) and nuisance metals (e.g., zinc). Anion species also become predominant in flyash produced by INEEL incineration, where chloride and sulfate are at concentrations that can approach 15-20 wt% each. In addition, treatment of the WERF flyash is further complicated by a significant fraction of ignitables composed of carbon soot and various hydrocarbon species that have been measured in some cases at 30% net by Loss-on-Ignition tests. Bottom ash produced at the WERF site is generally much less toxic, if not nontoxic, as compared to the flyash. Due to the complex composition of the flyash material, stabilization attempts at the INEEL have been only partly successful, causing the effectiveness and viability of treatment methods to be revisited. Breakthroughs in flyash stabilization came in 1998 when more complete characterization data gave us further insight into the chemical and physical nature of the flyash. These breakthroughs were also facilitated by the use of a computer model for electrolytes that allowed us to simulate stabilization options prior to started laboratory studies. This paper summarizes efforts at the INEEL, spanning the past three years, that have focused on stabilizing flyash. A brief history of INEEL treatability studies is given, showing that the degree of effective flyash stabilization was proportional to the amount of meaningful characterization data that was available. Various binders have been used in these treatability studies, including Portland cement type I/II, Portland cement type V, JGC Super Cement (blast furnace slag cement), a Fluid Tech

Technical reliability of geological disposal for high-level radioactive wastes in Japan. The second progress report. Part 2. Engineering technology for geological disposal

International Nuclear Information System (INIS)

1999-11-01

Based on the Advisory Committee Report on Nuclear Fuel Cycle Backend Policy submitted to the Japanese Government in 1997, JNC documents the progress of research and development program in the form of the second progress report (the first one published in 1992). It summarizes an evaluation of the technical reliability and safety of the deep geological disposal concept for high-level radioactive wastes (HLW) in Japan. The present document, part 2 of the progress report, concerns engineering aspect with reference to Japanese geological disposal plan, according to which the vitrified HLW will be disposed of into a deep, stable rock mass with thick containers and surrounding buffer materials at the depth of several hundred meters. It discusses on multi-barrier systems consisting of a series of engineered and natural barriers that will isolate radioactive nuclides effectively and retard their migrations to the biosphere environment. Performance of repository components, including specifications of containers for vitrified HLW and their overpacks under design as well as buffer material such as Japanese bentonite to be placed in between are described referring also to such possible problems as corrosion arising from the supposed system. It also presents plans and designs for underground disposal facilities, and the presumed management of the underground facilities. (Ohno, S.)

Safety assessment of HLW geological disposal system

International Nuclear Information System (INIS)

Naito, Morimasa

2006-01-01

that Japan is located in a tectonically active zone. Safety assessment for a disposal system differs from that for other engineered systems such as power stations in terms of: Extremely long timescales must be taken into account. Natural environments, which are heterogeneous and cover large spatial areas, must be evaluated. It is thus impossible to apply conventional engineering approaches, where an entire system is constructed and utilized in such a way as to demonstrate system safety. This is a problem specific to the safety assessment of geological disposal. Taking this into account, this paper describes a general methodology of safety assessment for geological system including presentation of a series of steps for the assessment with examples of JNC's H12 safety assessment. (author)

Environmentally compatible sewage sludge disposal; Umweltgerechte Klaerschlammentsorgung

Energy Technology Data Exchange (ETDEWEB)

Mueller, J. [Technische Univ. Braunschweig (Germany). Inst. fuer Mechanische Verfahrenstechnik; Schwedes, J. [Technische Univ. Braunschweig (Germany). Inst. fuer Mechanische Verfahrenstechnik

1997-09-01

Cleaning of municipal and industrial waste water is done by means of biological processes: micro-organisms degrade pollutants. The resulting products are, besides cleaned waste water, sewage sludge and surplus sludge. Their disposal involves ecological and economic problems. One approach to their partial disposal is their degradation in a digester. Approximately one half of the organic substance is converted by anaerobic bacteria into energy-rich biogas. Optimization of this digestion process accelerates the anaerobic degradation process, increases the accruing amount of digester gas and reduces the volume of digested sludge to be disposed of. With these objectives, the Institute fuer Mechanische Verfahrenstechnik is conducting research into the mechanical treatment of micro-organisms remaining in surplus sludge by means of different treatment devices. The project is sponsored under the programme of the Deutsche Forschungsgemeinschaft DFG ``Biological processes with dispersive solids``. Mechanical treatment renders the cell constituents exploitable to anaerobic bacteria; the resulting sludge degradation is more rapid and more complete. (orig./ABI) [Deutsch] Zur Reinigung haeuslicher und industrieller Abwaesser werden biologische Prozesse eingesetzt. Dabei sorgen Mikroorganismen fuer den Abbau der Verunreinigungen. Neben dem gereinigten Abwasser fallen Primaer- und Ueberschussschlamm an, deren Entsorgung oekologische und oekonomische Probleme verursacht. Ein Weg zur partiellen Beseitigung dieser Klaerschlaemme ist ihr Abbau in einem Faulbehaelter. Dabei wird etwa die Haelfe der organischen Substanz durch anaerobe Bakterien zu einem energiereichen Biogas umgewandelt. Eine Optimierung dieses Faulprozesses beinhaltet: 1. Beschleunigung des anaeroben Abbauprozesses, 2. Erhoehung der anfallenden Faulgasmenge und 3. Reduzierung der zu entsorgenden Faulschlammenge. Mit diesen Zielsetzungen wird am Institut fuer Mechanische Verfahrenstechnik im Rahmen der DFG

System for the hydrogeologic analysis of uranium mill waste disposal sites

International Nuclear Information System (INIS)

Osiensky, J.L.

1983-01-01

Most of the uranium mill wastes generated before 1977 are stored in unlined tailings ponds. Seepage from some of these ponds has been of sufficient severity that the US Nuclear Regulatory Commission (NRC) has required the installation of withdrawal wells to remove the contaminated groundwater. Uranium mill waste disposal facilities typically are located in complex hydrogeologic environments. This research was initiated in 1980 to analyze hydrogeologic data collected at seven disposal sites in the US that have experienced problems with groundwater contamination. The characteristics of seepage migration are site specific and are controlled by the hydrogeologic environment in the vicinity of each tailings pond. Careful monitoring of most seepage plumes was not initiated until approximately 1977. These efforts were accelerated as a consequence of the uranium Mill Tailings Act of 1979. Some of the data collected at uranium mill waste disposal sites in the past are incomplete and some were collected by methods that are outdated. Data frequently were collected in sequences which disrupted the continuity of the hydrogeologic analysis and decreased the effectiveness of the data collection programs. Evaluation of data collection programs for seven uranium mill waste disposal sites in the US has led to the development and presentation herein of a system for the hydrogeologic analysis of disposal sites

Considerations in managing the assessment of the Canadian nuclear fuel waste disposal concept

International Nuclear Information System (INIS)

Dormuth, K.W.; Gillespie, P.A.; Whitaker, S.H.

1992-01-01

This paper reports that in developing a concept for disposal of Canada's nuclear fuel waste, AECL has faced challenges because the acceptability of the concept must be established before a site is selected, no agency has been made responsible for implementing the concept if it is selected, and many stakeholders in the review must be satisfied if the concept is to be accepted. The challenges have thus far been met by a program that is well-integrated technically and administratively. However, interactions with stakeholders reviewing the concept present a problem in communication. The authors believe the nature of the nuclear fuel waste disposal issue calls for a cooperative rather than an adversarial approach to problem solving to efficiently deal with the requirements of all the stakeholders

Underground disposal of radioactive wastes

Energy Technology Data Exchange (ETDEWEB)

NONE

1979-08-15

Disposal of low- and intermediate-level radioactive wastes by shallow land burial, emplacement in suitable abandoned mines, or by deep well injection and hydraulic fracturing has been practised in various countries for many years. In recent years considerable efforts have been devoted in most countries that have nuclear power programmes to developing and evaluating appropriate disposal systems for high-level and transuranium-bearing waste, and to studying the potential for establishing repositories in geological formations underlaying their territories. The symposium, organized jointly by the IAEA and OECD's Nuclear Energy Agency in cooperation with the Geological Survey of Finland, provided an authoritative account of the status of underground disposal programmes throughout the world in 1979. It was evidence of the experience that has been gained and the comprehensive investigations that have been performed to study various options for the underground disposal of radioactive waste since the last IAEA/NEA symposium on this topic (Disposal of Radioactive Waste into the Ground) was held in 1967 in Vienna. The 10 sessions covered the following topics: National programme and general studies, Disposal of solid waste at shallow depth and in rock caverns, underground disposal of liquid waste by deep well injection and hydraulic fracturing, Disposal in salt formations, Disposal in crystalline rocks and argillaceous sediments, Thermal aspects of disposal in deep geological formations, Radionuclide migration studies, Safety assessment and regulatory aspects.

Critical groups and biospheres in the context of radioactive waste disposal. Fourth report of the working group on principles and criteria for radioactive waste disposal

International Nuclear Information System (INIS)

1999-04-01

Plans for disposing radioactive wastes have raised a number of unique and mostly philosophical problems, mainly due to the very long time-scales which have to be considered. This report is concerned with the choice of critical groups and associated biospheres for application in safety assessments for underground disposal of radioactive wastes. For assessment of safety in the far future, when human behaviour or biosphere conditions cannot be known with any certainty, it is proposed that a stylized approach be adopted. The approach is consistent with that adopted in areas of radiation protection where it is impracticable to establish the precise characteristics of exposed individuals

recent approaches for treating waste management problems in the frame of uncertainty using computer software packages

International Nuclear Information System (INIS)

Abdel Gwad, A.S.A.

2008-01-01

The large-scale industrialization of the 20 th century produced both positive and negative effects. One of the negative effects was the production of hazardous wastes as a result of manufacturing processes. Preventing, recycling, and disposing of these wastes in an environmentally sustainable manner presents a challenge for the 21 st century.The hazardous waste management (HWM) problem is defined as the combined decision of selecting the disposal method, sitting the disposal plants and deciding on the waste flow structure. The hazardous waste management problem has additional requirements depending on the selected disposal method. Each disposal method has different requirements. For land disposal, the main issue is leachate. The land disposal facility should guarantee the safety of nearby groundwater. For incineration plants, the main requirement is the satisfaction of air pollution standards at population centers.The thesis consists of five chapters: Chapter I presents a survey on some important concepts of the hazardous waste management problem. Chapter II introduces three different approaches for treating the HWM problem. In the first approach a mathematical model for treating HWM problem. Where the incineration process is used as a tool for disposing the hazardous waste is presented. The second one discusses a multi objective location-routing model for HWM problem. The third approach is concerned with present a waste fuel blending approach for treating the hazardous waste problem using goal programming. Chapter III presents three different applications for waste management problem. The first application is concerned with waste collection in Southern Italy. The second discusses the management of solid waste in the city of Regina, Canada, by using an interval parameter technique. The third one introduces the planning of waste management systems with economies of scale for the region of Hamilton, Ontario, Canada. Chapter IV is devoted to an optimization the model

Aspects of nuclear wastes disposal of use in teaching basic chemistry

International Nuclear Information System (INIS)

Choppin, G.R.

1994-01-01

In this paper the utilization of several aspects of chemical issues in nuclear wastes disposal proposals are discussed. Equilibrium speciation, complexation competition, the effect of pH and complexation on redox speciation, sorption on colloids, etc. are a few examples of the chemical behavior of fission products and actinide metals in natural aquatic systems. A brief review of the types of nuclear wastes in the US and the proposed methods of disposal are presented to reflect the diversity of chemical problems involved and the opportunities they offer to use open-quotes realclose quotes examples in teaching

Alternative disposal technologies for new low-level radioactive waste disposal/storage facilities at the Savannah River Plant

International Nuclear Information System (INIS)

Cook, J.R.

1987-01-01

A Draft Environmental Impact Statement for Waste Management Activities for groundwater protection has been prepared for the Savannah River Plant. Support documentation for the DEIS included an Environmental Information Document on new radioactive waste disposal and storage facilities in which possible alternative disposal technologies were examined in depth. Six technologies that would meet the needs of the Savannah River Plant that selected for description and analysis include near surface disposal, near surface disposal with exceptions, engineered storage, engineered disposal, vault disposal of untreated waste, and a combination of near surface disposal, engineered disposal, and engineered storage. 2 refs

Inverse problem in radionuclide transport

International Nuclear Information System (INIS)

Yu, C.

1988-01-01

The disposal of radioactive waste must comply with the performance objectives set forth in 10 CFR 61 for low-level waste (LLW) and 10 CFR 60 for high-level waste (HLW). To determine probable compliance, the proposed disposal system can be modeled to predict its performance. One of the difficulties encountered in such a study is modeling the migration of radionuclides through a complex geologic medium for the long term. Although many radionuclide transport models exist in the literature, the accuracy of the model prediction is highly dependent on the model parameters used. The problem of using known parameters in a radionuclide transport model to predict radionuclide concentrations is a direct problem (DP); whereas the reverse of DP, i.e., the parameter identification problem of determining model parameters from known radionuclide concentrations, is called the inverse problem (IP). In this study, a procedure to solve IP is tested, using the regression technique. Several nonlinear regression programs are examined, and the best one is recommended. 13 refs., 1 tab

Power plant waste disposals in open-cast mines

Energy Technology Data Exchange (ETDEWEB)

Herstus, J.; Stastny, J. [AGE s.r.o. - Aplikovana Geotechnika a Ekologie, Thamova (Czechoslovakia)

1995-12-01

High population density in Czech Republic has led, as well as in other countries, to strong NIMBY syndrome influencing the waste disposal location. The largest thermal power plants are situated in neighborhood of extensive open-cast brown coal mines with huge area covered by tipped clayey spoil. Such spoil areas, technically almost useless, are potential space for power giant waste disposal position. There are several limitations, based on specific structural features of tipped clayey spoil, influencing decision to use such area as site for waste disposal. Low shear strength and extremely high compressibility belong to the geotechnical limitations. High permeability of upper ten or more meters of tipped spoil and its changes with applied stress level belongs to transitional features between geotechnical and environmental limitations. The problems of ash and FGD products stabilized interaction with such subgrade represent environmental limitation. The paper reports about the testing procedure developed for thickness and permeability estimation of upper soil layer and gives brief review of laboratory and site investigation results on potential sites from point of view of above mentioned limitations. Also gives an outline how to eliminate the influence of unfavorable conditions.

Optimal Earth's reentry disposal of the Galileo constellation

Science.gov (United States)

Armellin, Roberto; San-Juan, Juan F.

2018-02-01

Nowadays there is international consensus that space activities must be managed to minimize debris generation and risk. The paper presents a method for the end-of-life (EoL) disposal of spacecraft in Medium Earth Orbit (MEO). The problem is formulated as a multiobjective optimisation one, which is solved with an evolutionary algorithm. An impulsive manoeuvre is optimised to reenter the spacecraft in Earth's atmosphere within 100 years. Pareto optimal solutions are obtained using the manoeuvre Δv and the time-to-reentry as objective functions to be minimised. To explore at the best the search space a semi-analytical orbit propagator, which can propagate an orbit for 100 years in few seconds, is adopted. An in-depth analysis of the results is carried out to understand the conditions leading to a fast reentry with minimum propellant. For this aim a new way of representing the disposal solutions is introduced. With a single 2D plot we are able to fully describe the time evolution of all the relevant orbital parameters as well as identify the conditions that enables the eccentricity build-up. The EoL disposal of the Galileo constellation is used as test case.

International safeguards concerns of Spent Fuel Disposal Program

International Nuclear Information System (INIS)

Pillay, K.K.S.

1988-01-01

The purpose of this paper is to stimulate discussions on the subjects of safeguarding large quantities of plutonium contained in spent fuels to be disposed of in geologic respositories. All the spent fuel disposal scenarios examined here pose a variety of safeguards problems, none of which are adequately addressed by the international safeguards community. The spent fuels from once-through fuel cycles in underground repositories would become an increasingly attractive target for diversion because of their plutonium content and decreasing radioactivity. Current design of the first geologic repository in the US will have the capacity to accommodate wastes equivalent to 70,000 Mt of uranium from commercial and defense fuel cycles. Of this, approximately 62,000 Mt uranium equivalent will be commerical spent fuel, containing over 500 Mt of plutonium. International safeguards commitments may require us to address the safeguards issues of disposing of such large quanities of plutonium in a geologic repository, which has the potential to become a plutonium mine in the future. This paper highlights several issues that should be addressed in the near term by US industries and the DOE before geologic repositories for spent fuels become a reality

Low-level radioactive mixed waste land disposal facility -- Permanent disposal

International Nuclear Information System (INIS)

Erpenbeck, E.G.; Jasen, W.G.

1993-03-01

Radioactive mixed waste (RMW) disposal at US Department of Energy (DOE) facilities is subject to the Resource Conservation and Recovery Act of 1976 (RCRA) and the Hazardous and Solid Waste Amendments of 1984 (HSWA). Westinghouse Hanford Company, in Richland, Washington, has completed the design of a radioactive mixed waste land disposal facility, which is based on the best available technology compliant with RCRA. When completed, this facility will provide permanent disposal of solid RMW, after treatment, in accordance with the Land Disposal Restrictions. The facility includes a double clay and geosynthetic liner with a leachate collection system to minimize potential leakage of radioactive or hazardous constituents from the landfill. The two clay liners will be capable of achieving a permeability of less than 1 x 10 -7 cm/s. The two clay liners, along with the two high density polyethylene (HDPE) liners and the leachate collection and removal system, provide a more than conservative, physical containment of any potential radioactive and/or hazardous contamination

Radiological waste problems

International Nuclear Information System (INIS)

Milanov, M.

1990-01-01

The chapter offers a description of the system of radioactive waste treatment as presented in the Belene NPP technical project and goes beyond the scope of the project evaluation in the account of the radioactive waste treatment, storage and disposal of other sources including the industry, science and the medicine of Bulgaria. The necessity for a developed legislative basis and an accepted policy regarding the radioactive waste management in the country is stressed upon. There is an elaboration on the problem of the construction of a new radioactive waste depository, the capacities of the existing disposal site being used up. 17 refs., 7 tabs. (R.Ts.)

Uncertainties about the safety of disposal leading to a wish to keep alternatives open. Discussion on the concepts 'storage' ('wait and see') vs. 'disposal' and 'retrievable disposal' vs. 'definitive disposal'

International Nuclear Information System (INIS)

Norrby, S.

2000-01-01

Uncertainties about the safety of final disposal may lead to unwillingness to take decisions about waste management issues that may seem to be non-reversible. This has lead to proposals that we should wait with decisions on final measures and instead store the waste for some period of time. Also the possibility of retrieval may lead to decisions not to go for permanent disposal but instead to retrievable disposal. These aspects and the pros and cons are discussed both from a more general perspective and also with some reflections from the Swedish programme for nuclear waste management and disposal. (author)

Study on high-level waste geological disposal metadata model

International Nuclear Information System (INIS)

Ding Xiaobin; Wang Changhong; Zhu Hehua; Li Xiaojun

2008-01-01

This paper expatiated the concept of metadata and its researches within china and abroad, then explain why start the study on the metadata model of high-level nuclear waste deep geological disposal project. As reference to GML, the author first set up DML under the framework of digital underground space engineering. Based on DML, a standardized metadata employed in high-level nuclear waste deep geological disposal project is presented. Then, a Metadata Model with the utilization of internet is put forward. With the standardized data and CSW services, this model may solve the problem in the data sharing and exchanging of different data form A metadata editor is build up in order to search and maintain metadata based on this model. (authors)

Study on risk communication support system of geological disposal

International Nuclear Information System (INIS)

Higuchi, Natsuko; Yoshizawa, Yuji; Takeuchi, Mitsuo; Kitayama, Kazumi; Kobayashi, Yoko

2008-01-01

In order to smoothly implement the selection of a final site for disposal of high-level radioactive waste (HLW), it is necessary to ensure effective communication with various stakeholders and to gain public confidence. Text mining technology can extract useful information from texts such as symposium dialogs or questionnaires after a lecture. The problem and its solution are extracted by structuring and visualizing the topics and it is possible to obtain feedback information for the next symposium or lecture and/or posterity. We applied text mining to analyze a facilitation of panel discussion and to understand future researchers. The development of such an analysis technique will contribute to mutual confidence and agreement among all the stakeholders in a HLW disposal project. (author)

Institutional aspects of siting nuclear waste disposal facilities in the United States

International Nuclear Information System (INIS)

Stewart, J.C.; Prichard, W.C.

1987-01-01

This paper has dealt with the institutional issues associated with disposal of nuclear waste in the US. The authors believe that these institutional problems must be resolved, no matter how technologically well suited a site may be for disposal, before site selection may take place. The authors have also pointed out that the geography of the US, with its large arid regions of very low population density, contributes to the institutional acceptability of nuclear waste disposal. Economic factors, especially in sparsely populated areas where the uranium mining and milling industry has caused operation, also weigh on the acceptability of nuclear waste to local communities. This acceptability will be highest where there are existing nuclear facilities and/or facilities which are closed - thus creating unemployment especially where alternative economic opportunities are few

Perspectives of sewage sludge disposal. Technical meeting; Perspektiven der Klaerschlammentsorgung. Fachtagung

Energy Technology Data Exchange (ETDEWEB)

Wilderer, P.A. [ed.; Faulstich, M. [ed.; Rothemund, C. [ed.; Angerhoefer, R. [ed.

1996-10-01

Sewage sludge is a material requiring utilization and disposal. A profound change is due with the prohibition from the year 2005 to deposit untreated sewage sludge at landfills. As it will hardly be possible to use all sewage sludge in farming, thermal disposal will be indispensable. A major problem consists in forecasting the quantities of sewage sludge requiring processing and determining the corresponding plant capacities. If the problem is varied, so are the solutions offered. Therefore, a final panel discussion was held where representatives of science, the ministries and the interest groups concerned had the possibility to voice their opinions. (orig.) [Deutsch] Es gilt Klaerschlaemme zu verwerten und zu entsorgen. Hier ist eine nachhaltige Veraenderung vor allem deshalb zu erwarten, da ab dem Jahr 2005 die Ablagerung nicht vorbehandelter Klaerschlaemme untersagt ist. Da aber kaum saemtliche Klaerschlaemme landwirtschaftlich zu verwerten sind, ist das Standbein thermische Behandlung unverzichtbar. Ein grundsaetzliches Problem ist hier die Prognose der zukuenftig zu behandelnden Mengen und des sich daraus ergebenden Anlagenbedarfs. So vielfaeltig wie das Problem, so vielfaeltig sind die Auffassungen zur Loesung desselben. In einer abschliessenden Podiumsdiskussion hatten daher Vertreter der Wissenschaft, der Ministerien sowie der einschlaegigen Interessenverbaende die Moeglichkeit, ihre Positionen zu verdeutlichen. (orig.)

Suggestions on R and D work of high-level radioactive waste disposal in China

International Nuclear Information System (INIS)

Xu Guoqing

2012-01-01

The difference between repository and generic underground facilities is described. Some differences and similarities of site selection between the low and medium radioactive waste disposal, nuclear power station and high-level radioactive waste repository are also discussed here. We trend to extremely emphasize the safety of high-level radioactive waste disposal because of high toxicity, long half-life and long safety disposal period of this kind of radioactive wastes; because radioactive waste in the repository is of high specific activities and buried in depth, it would be difficult to meddle with its safety. In case of repository system being destroyed, the author considers that in the stages of regional and area site selection, the first task is to investigate regional tectonic stability. Some problems about disposal options and others are also discussed in this paper. (author)

Unreviewed Disposal Question Evaluation: Waste Disposal In Engineered Trench #3

Energy Technology Data Exchange (ETDEWEB)

Hamm, L. L.; Smith, F. G. III; Flach, G. P.; Hiergesell, R. A.; Butcher, B. T.

2013-07-29

Because Engineered Trench #3 (ET#3) will be placed in the location previously designated for Slit Trench #12 (ST#12), Solid Waste Management (SWM) requested that the Savannah River National Laboratory (SRNL) determine if the ST#12 limits could be employed as surrogate disposal limits for ET#3 operations. SRNL documented in this Unreviewed Disposal Question Evaluation (UDQE) that the use of ST#12 limits as surrogates for the new ET#3 disposal unit will provide reasonable assurance that Department of Energy (DOE) 435.1 performance objectives and measures (USDOE, 1999) will be protected. Therefore new ET#3 inventory limits as determined by a Special Analysis (SA) are not required.

Water Resources Research Program. Abatement of malodors at diked, dredged-material disposal sites. Final report

Energy Technology Data Exchange (ETDEWEB)

Harrison, W.; Dravnieks, A.; Zussman, R.; Goltz, R.

1976-06-01

Samples of malodorous air and dredged material were collected at diked disposal sites at the following locations: Buffalo, NY; Milwaukee, WI; Mobile, AL; York Harbor, ME; Houston, TX; Detroit, MI; and Anacortes, WA; during the period July--October, 1975. Odorous compounds in the air samples were identified by gas chromatography/mass spectrometry, while the detection threshold, intensity, and character of the various odors were determined by experienced panelists using a dynamic, forced-choice-triangle olfactometer. Although significant problems with malodors were not observed beyond the disposal-area dikes during site visits, noteworthy odor episodes had occurred at some sites. An odor-abatement strategy is presented for handling the expected range of odor conditions at dredged-material disposal sites. Its aim is to reduce to an acceptable level the intensity of malodors in an affected community. The main steps in the strategy cover selection of the disposal site, site preparation, odor characterization of sediments to be dredged, malodor abatement during dredging and disposal operations, malodor abatement after filling of the disposal site, and the handling of malodor complaints.

Subsurface waste disposal by means of wells - A selective annotated bibliography

Science.gov (United States)

Rima, Donald Robert; Chase, Edith B.; Myers, Beverly M.

1971-01-01

Subsurface waste disposal by means of wells is the practice of using drilled wells to inject unwanted substances into underground rock formations. The use of wells for this purpose is not a new idea. As long ago as the end of the last century, it was common practice to drill wells for the express purpose of draining swamps and small lakes to reclaim the land for agricultural purposes. A few decades later in the 1920's and 1930's many oil companies began using injection wells to dispose of oil-field brines and to repressurize oil reservoirs. During World War II, the Atomic Energy Commission began using injection wells to dispose of certain types of radioactive wastes. More recently, injection wells have been drilled to dispose of a variety of byproducts of industrial processes. The number of such wells has increased rapidly since Congress passed the Clean Streams Act of 1966, which restricted the discharge of waste into surface waters.Many scientists and public officials question the propriety of using the term "disposal" when referring to the underground injection of wastes. Their reasons are that underground injection is not, as many advocates claim, "a complete and final answer" to the waste-disposal problem. Rather, it is merely a process wherein the injected wastes are committed to the subsurface with uncertainty as to their ultimate fate or limits of confinement. In effect, the wastes, undiminished and unchanged, are removed from the custody of man and placed in the custody of nature.Although the concept of waste-injection wells is relatively simple, the effects of waste injection can be very complex, particularly when dealing with the exotic and complex components of some industrial wastes. Besides the physical forces of injection, there are many varied interactions between the injected wastes and the materials within the injection zone. Because these changes occur out of sight in the subsurface, they are difficult to assess and not generally understood. In

Waste disposal in Europe - Looking ahead

International Nuclear Information System (INIS)

Verkerk, B.

1985-01-01

In this introductory paper a short outline is given of the Commission's programme on management and disposal of radioactive waste, followed by a discussion of the programme structure. This leads to the very important aspect of evaluation of results obtained and the communication of the achievements to the outer world. The important role of the media in this respect is stressed. Looking ahead, an important part of the Third Five years programme, the development of demonstration facilities, is projected against the problem of acceptability. Thinking about the consequences of entering the demonstration stage with respect to future research it turns out to be a broad field of work opens up, when the achievements reached in the radioactive waste area, could be transferred to problems of other toxic wastes and fusion wastes

Institutional storage and disposal of radioactive materials

International Nuclear Information System (INIS)

St Germain, J.

1986-01-01

Storage and disposal of radioactive materials from nuclear medicine operations must be considered in the overall program design. The storage of materials from daily operation, materials in transit, and long-term storage represent sources of exposure. The design of storage facilities must include consideration of available space, choice of material, occupancy of surrounding areas, and amount of radioactivity anticipated. Neglect of any of these factors will lead to exposure problems. The ultimate product of any manipulation of radioactive material will be some form of radioactive waste. This waste may be discharged into the environment or placed within a storage area for packaging and transfer to a broker for ultimate disposal. Personnel must be keenly aware of packaging regulations of the burial site as well as applicable federal and local codes. Fire codes should be reviewed if there is to be storage of flammable materials in any area. Radiation protection personnel should be aware of community attitudes when considering the design of the waste program

Study on the background information for the R and D of geological disposal

International Nuclear Information System (INIS)

Matsui, Kazuaki; Hirusawa, Shigenobu; Komoto, Harumi

2001-02-01

It is quite important for Japan Nuclear Cycle Development Institute (JNC) to analyze the R and D items after 'H12 report' and also provide their results of R and D activities to general public effectively. Recognizing the importance of the social consensus to the geological disposal, relating background informations were to be picked up. In this fiscal year, following two main topics were selected and studied. 1. Research and analysis on the options for the geological disposal concept. The major nuclear power-generating countries have almost all chosen deep geological disposal as preferred method for HLW disposal. Since 1990's, to make the geological disposal flexible, the alternative concepts for the disposal of HLW have been discussed promoting the social acceptance. In this context, recent optional discussions and international evaluations on the following topics were studied and summarized. (1) Reversibility of waste disposal/Retrievability of waste/Waste monitoring, (2) Long-term storage concept and its effectiveness, (3) Present position and role of international disposal. 2. Research and analysis on some educational materials collected from foreign countries. Although geological disposals is scheduled to start still in future, it is quite important to study the procedures to attract younger generation and get their proper perceptions on the nuclear energy and waste problems. As the supporting analysis to implement strategically the public relational activities for JNC's geological disposal R and D, particular attention was focused on the educational materials obtained in the last year's survey. Representative educational materials were selected and following items were studied and summarized. (1) Basic approach, positioning and characteristics of the educational materials, (2) Detailed analysis of the representatively selected educational materials, (3) Comparison of the analyzed characteristics and study on its feedback to Japanese materials. (author)

Students' Preconceptions about Urban Environmental Problems and Solid Waste.

Science.gov (United States)

Membiela, Pedro; And Others

1993-01-01

Examined students' preconceptions about environmental problems in cities, particularly that of urban disposable waste. They found that students' ideas were dominated by what they perceived, without regard to existing interactions, and that students were unaware of the fundamental role of reuse and recycling in the solution of the disposal of solid…

Toxic and hazardous waste disposal. Volume 4. New and promising ultimate disposal options

International Nuclear Information System (INIS)

Pojasek, R.B.

1980-01-01

Separate abstrats were prepared for four of the eighteen chapters of this book which reviews several disposal options available to the generators of hazardous wastes. The chapters not abstracted deal with land disposal of hazardous wastes, the solidification/fixation processes, waste disposal by incineration and molten salt combustion and the use of stabilized industrial waste for land reclamation and land farming

Legal system of nuclear waste disposal. Das System der atomaren Entsorgungsregelung

Energy Technology Data Exchange (ETDEWEB)

Dauk, W

1983-01-01

This doctoral thesis presents solutions to some of the legal problems encountered in the interpretation of the various laws and regulations governing nuclear waste disposal, and reveals the legal system supporting the variety of individual regulations. Proposals are made relating to modifications of problematic or not well defined provisions, in order to contribute to improved juridical security, or inambiguity in terms of law. The author also discusses the question of the constitutionality of the laws for nuclear waste disposal. Apart from the responsibility of private enterprise to contribute to safe treatment or recycling, within the framework of the integrated waste management concept, and apart from the Government's responsibility for interim or final storage of radioactive waste, there is a third possibility included in the legal system for waste management, namely voluntary measures taken by private enterprise for radioactive waste disposal. The licence to be applied for in accordance with section 3, sub-section (1) of the Radiation Protection Ordinance is interpreted to pertain to all measures of radioactive waste disposal, thus including final storage of radioactive waste by private companies. Although the terminology and systematic concept of nuclear waste disposal are difficult to understand, there is a functionable system of legal provisions contained therein. This system fits into the overall concept of laws governing technical safety and safety engineering.

Report on radioactive waste disposal

International Nuclear Information System (INIS)

1993-01-01

The safe management of radioactive wastes constitutes an essential part of the IAEA programme. A large number of reports and conference proceedings covering various aspects of the subject have been issued. The Technical Review Committee on Underground Disposal (February 1988) recommended that the Secretariat issue a report on the state of the art of underground disposal of radioactive wastes. The Committee recommended the need for a report that provided an overview of the present knowledge in the field. This report covers the basic principles associated with the state of the art of near surface and deep geological radioactive waste disposal, including examples of prudent practice, and basic information on performance assessment methods. It does not include a comprehensive description of the waste management programmes in different countries nor provide a textbook on waste disposal. Such books are available elsewhere. Reviewing all the concepts and practices of safe radioactive waste disposal in a document of reasonable size is not possible; therefore, the scope of this report has been limited to cover essential parts of the subject. Exotic disposal techniques and techniques for disposing of uranium mill tailings are not covered, and only brief coverage is provided for disposal at sea and in the sea-bed. The present report provides a list of references to more specialized reports on disposal published by the IAEA as well as by other bodies, which may be consulted if additional information is sought. 108 refs, 22 figs, 2 tabs

Korean Reference HLW Disposal System

Energy Technology Data Exchange (ETDEWEB)

Choi, Heui Joo; Lee, J. Y.; Kim, S. S. (and others)

2008-03-15

This report outlines the results related to the development of Korean Reference Disposal System for High-level radioactive wastes. The research has been supported around for 10 years through a long-term research plan by MOST. The reference disposal method was selected via the first stage of the research during which the technical guidelines for the geological disposal of HLW were determined too. At the second stage of the research, the conceptual design of the reference disposal system was made. For this purpose the characteristics of the reference spent fuels from PWR and CANDU reactors were specified, and the material and specifications of the canisters were determined in term of structural analysis and manufacturing capability in Korea. Also, the mechanical and chemical characteristics of the domestic Ca-bentonite were analyzed in order to supply the basic design parameters of the buffer. Based on these parameters the thermal and mechanical analysis of the near-field was carried out. Thermal-Hydraulic-Mechanical behavior of the disposal system was analyzed. The reference disposal system was proposed through the second year research. At the final third stage of the research, the Korean Reference disposal System including the engineered barrier, surface facilities, and underground facilities was proposed through the performance analysis of the disposal system.

Disposal options for radioactive waste

International Nuclear Information System (INIS)

Olivier, J.P.

1991-01-01

On the basis of the radionuclide composition and the relative toxicity of radioactive wastes, a range of different options are available for their disposal. Practically all disposal options rely on confinement of radioactive materials and isolation from the biosphere. Dilution and dispersion into the environment are only used for slightly contaminated gaseous and liquid effluents produced during the routine operation of nuclear facilities, such as power plants. For the bulk of solid radioactive waste, whatever the contamination level and decay of radiotoxicity with time are, isolation from the biosphere is the objective of waste disposal policies. The paper describes disposal approaches and the various techniques used in this respect, such as shallow land burial with minimum engineered barriers, engineered facilities built at/near the surface, rock cavities at great depth and finally deep geologic repositories for long-lived waste. The concept of disposing long-lived waste into seabed sediment layers is also discussed, as well as more remote possibilities, such as disposal in outer space or transmutation. For each of these disposal methods, the measures to be adopted at institutional level to reinforce technical isolation concepts are described. To the extent possible, some comments are made with regard to the applicability of such disposal methods to other hazardous wastes. (au)

Underground disposal of radioactive wastes

International Nuclear Information System (INIS)

1981-01-01

This report is an overview document for the series of IAEA reports dealing with underground waste disposal to be prepared in the next few years. It provides an introduction to the general considerations involved in implementing underground disposal of radioactive wastes. It suggests factors to be taken into account for developing and assessing waste disposal concepts, including the conditioned waste form, the geological containment and possible additional engineered barriers. These guidelines are general so as to cover a broad range of conditions. They are generally applicable to all types of underground disposal, but the emphasis is on disposal in deep geological formations. Some information presented here may require slight modifications when applied to shallow ground disposal or other types of underground disposal. Modifications may also be needed to reflect local conditions. In some specific cases it may be that not all the considerations dealt with in this book are necessary; on the other hand, while most major considerations are believed to be included, they are not meant to be all-inclusive. The book primarily concerns only underground disposal of the wastes from nuclear fuel cycle operations and those which arise from the use of isotopes for medical and research activities

ENVIRONMENTALLY SOUND DISPOSAL OF RADIOACTIVE MATERIALS AT A RCRA HAZARDOUS WASTE DISPOSAL FACILITY

International Nuclear Information System (INIS)

Romano, Stephen; Welling, Steven; Bell, Simon

2003-01-01

The use of hazardous waste disposal facilities permitted under the Resource Conservation and Recovery Act (''RCRA'') to dispose of low concentration and exempt radioactive materials is a cost-effective option for government and industry waste generators. The hazardous and PCB waste disposal facility operated by US Ecology Idaho, Inc. near Grand View, Idaho provides environmentally sound disposal services to both government and private industry waste generators. The Idaho facility is a major recipient of U.S. Army Corps of Engineers FUSRAP program waste and received permit approval to receive an expanded range of radioactive materials in 2001. The site has disposed of more than 300,000 tons of radioactive materials from the federal government during the past five years. This paper presents the capabilities of the Grand View, Idaho hazardous waste facility to accept radioactive materials, site-specific acceptance criteria and performance assessment, radiological safety and environmental monitoring program information

Geographic factors related to site suitability of low-level waste disposal

International Nuclear Information System (INIS)

Zittel, H.E.

1981-01-01

A number of factors related to the site suitability of low-level waste disposal sites are discussed. The factors are a combination of those which might be considered environmental and those dealing with site criteria. Among the factors covered are: possible population criteria, alternative site selection, transportation criteria and community involvement considerations. All these factors are discussed in a manner based on the premise that the technology exists to carry out low-level waste disposal in a manner such that public health and safety can be insured. The conclusion of the discussion is that problems encountered in siting low-level waste facilities will be largely societal and political in nature

Transuranic advanced disposal systems: preliminary 239Pu waste-disposal criteria for Hanford

International Nuclear Information System (INIS)

Kennedy, W.E. Jr.; Napier, B.A.; Soldat, J.K.

1982-08-01

An evaluation of the feasibility and potential application of advanced disposal systems is being conducted for defense transuranic (TRU) wastes at the Hanford Site. The advanced waste disposal options include those developed to provide greater confinement than provided by shallow-land burial. An example systems analysis is discussed with assumed performance objectives and various Hanford-specific disposal conditions, waste forms, site characteristics, and engineered barriers. Preliminary waste disposal criteria for 239 Pu are determined by applying the Allowable Residual Contamination Level (ARCL) method. This method is based on compliance with a radiation dose rate limit through a site-specific analysis of the potential for radiation exposure to individuals. A 10,000 year environmental performance period is assumed, and the dose rate limit for human intrusion is assumed to be 500 mrem/y to any exposed individual. Preliminary waste disposal criteria derived by this method for 239 Pu in soils at the Hanford Site are: 0.5 nCi/g in soils between the surface and a depth of 1 m, 2200 nCi/g of soil at a depth of 5 m, and 10,000 nCi/g of soil at depths 10 m and below. These waste disposal criteria are based on exposure scenarios that reflect the dependence of exposure versus burial depth. 2 figures, 5 tables

Using Automation to Monitor and Report Hazardous Waste Disposal Costs: A Mission-Critical Obligation

National Research Council Canada - National Science Library

Hassrick, H

1996-01-01

Controlling, monitoring, and reporting hazardous waste disposal costs has become increasingly important as environmental problems arise, costs escalate, and budgets contract. In FY94, the U.S. Army, Europe (USAREUR), spent...

Storage and disposal of nuclear wastes: prospects for the next 25 years

International Nuclear Information System (INIS)

Lyons, W.C.

1978-01-01

This paper discusses the processing, handling, storage, and disposal options available for both commercial high-level radioactive wastes and defense radioactive wastes. A review is made of the past performance of government in finding solutions for these pressing problems. The present inventory of commercial and defense waste is discussed and the inventory for the near future projected. The relationships between storage and disposal technologies and the commercial and defense wastes are discussed. It is suggested that the commercial fuel cycle will be delayed as long as defense and commercial wastes disposal technologies are not demonstrated. An assessment is made as to which technologies and techniques appear to be the most useful for accomplishing the critical near term task of isolating the defense wastes. A discussion is then made as to how these technologies and techniques will be used for the commercial fuel cycle

Institutional aspects of siting nuclear waste disposal facilities in the United States

International Nuclear Information System (INIS)

Stewart, John Cameron.; Prichard, Clark. W.

1987-01-01

This chapter deals with the institutional issues associated with the disposal of nuclear waste in the United States of America. These include socio-economic, financial, land use and especially, political factors. Institutional issues must, however, be resolved, as well as the technological problems of engineering and geology. The general issues are first examined, then the organisation and financing, land use, community acceptance, transport problems and finally, local economic impacts. (UK)

Nuclear fuel waste disposal

International Nuclear Information System (INIS)

Allan, C.J.

1993-01-01

The Canadian concept for nuclear fuel waste disposal is based on disposing of the waste in a vault excavated 500-1000 m deep in intrusive igneous rock of the Canadian Shield. The author believes that, if the concept is accepted following review by a federal environmental assessment panel (probably in 1995), then it is important that implementation should begin without delay. His reasons are listed under the following headings: Environmental leadership and reducing the burden on future generations; Fostering public confidence in nuclear energy; Forestalling inaction by default; Preserving the knowledge base. Although disposal of reprocessing waste is a possible future alternative option, it will still almost certainly include a requirement for geologic disposal

Selection of the trajectory for radioactive wastes disposal in the outer space

International Nuclear Information System (INIS)

Pshenin, E.; Suimenbaev, B.

1996-01-01

Concept of reliable and safe disposal of highly active wastes have not yet been developed in any country, this does not allow to finally remove them and restricts development of nuclear energetic in developed countries. The solution of this problem is removal of the wastes of nuclear production outside of the earth. In this connection a proposal of disposal of radioactive wastes on the sun seems to be very interesting though rather exotic. The wastes can be delivered there by spaceships using infrastructure of the USSR nuclear space complex on the territory of Kazakstan [1]. The main problem considered in the present project is providing of ecological safety of removal of radioactive wastes. It includes measures on providing ecological safety during the removal: - at the stage of launching of a spaceship; - at the stage of injection of the of a spaceship to an intermediate orbit; - during inter orbital flights

Should the U.S. proceed to consider licensing deep geological disposal of high-level nuclear waste

International Nuclear Information System (INIS)

Curtiss, J.R.

1993-01-01

The United States, as well as other countries facing the question of how to handle high-level nuclear waste, has decided that the most appropriate means of disposal is in a deep geologic repository. In recent years, the Radioactive Waste Management Committee of the Nuclear Energy Agency has developed several position papers on the technical achievability of deep geologic disposal, thus demonstrating the serious consideration of deep geologic disposal in the international community. The Committee has not, as yet, formally endorsed disposal in a deep geologic repository as the preferred method of handling high-level nuclear waste. The United States, on the other hand, has studied the various methods of disposing of high-level nuclear waste, and has determined that deep geologic disposal is the method that should be developed. The purpose of this paper is to present a review of the United States' decision on selecting deep geologic disposal as the preferred method of addressing the high-level waste problem. It presents a short history of the steps taken by the U.S. in determining what method to use, discusses the NRC's waste Confidence Decision, and provides information on other issues in the U.S. program such as reconsideration of the final disposal standard and the growing inventory of spent fuel in storage

A quantitative analysis of municipal solid waste disposal charges in China.

Science.gov (United States)

Wu, Jian; Zhang, Weiqian; Xu, Jiaxuan; Che, Yue

2015-03-01

Rapid industrialization and economic development have caused a tremendous increase in municipal solid waste (MSW) generation in China. China began implementing a policy of MSW disposal fees for household waste management at the end of last century. Three charging methods were implemented throughout the country: a fixed disposal fee, a potable water-based disposal fee, and a plastic bag-based disposal fee. To date, there has been little qualitative or quantitative analysis on the effectiveness of this relatively new policy. This paper provides a general overview of MSW fee policy in China, attempts to verify whether the policy is successful in reducing general waste collected, and proposes an improved charging system to address current problems. The paper presents an empirical statistical analysis of policy effectiveness derived from an environmental Kuznets curve (EKC) test on panel data of China. EKC tests on different kinds of MSW charge systems were then examined for individual provinces or cities. A comparison of existing charging systems was conducted using environmental and economic criteria. The results indicate the following: (1) the MSW policies implemented over the study period were effective in the reduction of waste generation, (2) the household waste discharge fee policy did not act as a strong driver in terms of waste prevention and reduction, and (3) the plastic bag-based disposal fee appeared to be performing well according to qualitative and quantitative analysis. Based on current situation of waste discharging management in China, a three-stage transitional charging scheme is proposed and both advantages and drawbacks discussed. Evidence suggests that a transition from a fixed disposal fee to a plastic bag-based disposal fee involving various stakeholders should be the next objective of waste reduction efforts.

Safety considerations in the disposal of disused sealed radioactive sources in borehole facilities

International Nuclear Information System (INIS)

2003-08-01

Sealed radioactive sources are used in medicine, industry and research for a wide range of purposes. They can contain different radionuclides in greatly varying amounts. At the end of their useful lives, they are termed 'disused sources' but their activity levels can still be quite high. They are, for all practical purposes, another type of radioactive waste that needs to be disposed of safely. Disused sealed radioactive sources can represent a significant hazard to people if not managed properly. Many countries have no special facilities for the management or disposal of radioactive waste, as they have no nuclear power programmes requiring such facilities. Even in countries with developed nuclear programmes, disused sealed sources present problems as they often fall outside the common categories of radioactive waste for which disposal options have been identified. As a result, many disused sealed sources are kept in storage. Depending on the nature of the storage arrangements, this situation may represent a high potential risk to workers and to the public. The IAEA has received numerous requests for assistance from Member States faced with the problem of safely managing disused sealed sources. The requests have related to both technical and safety aspects. Particularly urgent requests have involved emergency situations arising from unsafe storage conditions and lost sources. There is therefore an important requirement for the development of safe and cost-effective final disposal solutions. Consequently, a number of activities have been initiated by the IAEA to assist Member States in the management of disused sealed sources. The objective of this report is to address safety issues relevant to the disposal of disused sealed sources, and other limited amounts of radioactive waste, in borehole facilities. It is the first in a series of reports aiming to provide an indication of the present issues related to the use of borehole disposal facilities to safely disposal

Waste-Mixes Study for space disposal

International Nuclear Information System (INIS)

McCallum, R.F.; Blair, H.T.; McKee, R.W.; Silviera, D.J.; Swanson, J.L.

1983-01-01

The Wastes Mixes Study is a component of Cy-1981 and 1982 research activities to determine if space disposal could be a feasible complement to geologic disposal for certain high-level (HLW) and transuranic wastes (TRU). The objectives of the study are: to determine if removal of radionuclides from HLW and TRU significantly reduces the long-term radiological risks of geologic disposal; to determine if chemical partitioning of the waste for space disposal is technically feasible; to identify acceptable waste forms for space disposal; and to compare improvements in geologic disposal system performance to impacts of additional treatment, storage, and transportation necessary for space disposal. To compare radiological effects, five system alternatives are defined: Reference case - All HLW and TRU to a repository. Alternative A - Iodine to space, the balance to a repository. Alternative B - Technetium to space, the balance to a repository. Alternative C - 95% of cesium and strontium to a repository; the balance of HLW aged first, then to space; plutonium separated from TRU for recycle; the balance of the TRU to a repository. Alternative D - HLW aged first, then to space, plutonium separated from TRU for recycle; the balance of the TRU to a repository. The conclusions of this study are: the incentive for space disposal is that it offers a perception of reduced risks rather than significant reduction. Suitable waste forms for space disposal are cermet for HLW, metallic technetium, and lead iodide. Space disposal of HLW appears to offer insignificant safety enhancements when compared to geologic disposal; the disposal of iodine and technetium wastes in space does not offer risk advantages. Increases in short-term doses for the alternatives are minimal; however, incremental costs of treating, storing and transporting wastes for space disposal are substantial

Argentine project for the final disposal of high-level radioactive wastes

International Nuclear Information System (INIS)

Palacios, E.; Ciallella, N.R.; Petraitis, E.J.

1989-01-01

From 1980 Argentina is carrying out a research program on the final disposal of high level radioactive wastes. The quantity of wastes produced will be significant in next century. However, it was decided to start with the studies well in advance in order to demonstrate that the high level wastes could be disposed in a safety way. The option of the direct disposal of irradiated fuel elements was discarded, not only by the energetic value of the plutonium, but also for ecological reasons. In fact, the presence of a total inventory of actinides in the non-processed fuel would imply a more important radiological impact than that caused if the plutonium is recycled to produce energy. The decision to solve the technological aspects connected with the elimination of high-level radioactive wastes well in advance, was made to avoid transfering the problem to future generations. This decision is based not only on technical evaluations but also on ethic premises. (Author)

Treated Effluent Disposal Facility

Data.gov (United States)

Federal Laboratory Consortium — Treated non-hazardous and non-radioactive liquid wastes are collected and then disposed of through the systems at the Treated Effluent Disposal Facility (TEDF). More...

Biomedical waste management - problems and perspectives: legal, administrative and fiscal viewpoint

International Nuclear Information System (INIS)

Jayaraman, S.; Philip, P.C.; Stephens, R.

1983-01-01

In recent years, the costs for the disposal of low level radioactive wastes have escalated and the states in which commercial waste disposal sites are located have also been insisting on ''hold harmless'' and indemnity agreements from the users of such sites. Coupled with the above, the uncertainty associated with the sites being kept open, has created a significant problem for the generators of low level wastes, forcing them to look for alternatives such as incineration. This paper attempts to provide an insight into the problem of low level radioactive wastes disposal from the legal, administrative and fiscal viewpoint as it pertains to statesupported teaching medical institution. Some aspects of public relations are also covered

The final disposal facility of spent nuclear fuel

International Nuclear Information System (INIS)

Prvakova, S.; Necas, V.

2001-01-01

Today the most serious problem in the area of nuclear power engineering is the management of spent nuclear fuel. Due to its very high radioactivity the nuclear waste must be isolated from the environment. The perspective solution of nuclear fuel cycle is the final disposal into geological formations. Today there is no disposal facility all over the world. There are only underground research laboratories in the well developed countries like the USA, France, Japan, Germany, Sweden, Switzerland and Belgium. From the economical point of view the most suitable appears to build a few international repositories. According to the political and social aspect each of the country prepare his own project of the deep repository. The status of those programmes in different countries is described. The development of methods for the long-term management of radioactive waste is necessity in all countries that have had nuclear programmes. (authors)

Legal aspects of sub-seabed disposal of radioactive waste

International Nuclear Information System (INIS)

Reyners, P.

1981-10-01

In connection with methods for disposal of highly radioactive waste, that consisting of burying such waste in the sub-seabed arouses an increasingly marked interest among specialists. Apart from the technical difficulties still to be overcome and current safety assessments, this method gives rise to quite considerable legal and political problems. Their solution will undoubtedly have a bearing on its chances of being implemented. (NEA) [fr

Identification of Human Intrusion Types into Radwaste Disposal Facility

International Nuclear Information System (INIS)

Budi Setiawan

2007-01-01

Human intrusion has long been recognized as a potentially important post-closure safety issue for rad waste disposal facility. It is due to the difficulties in predicting future human activities. For the preliminary study of human intrusion, identification of human intrusion types need to be recognized and investigated also the approaching of problem solving must be known to predict the prevention act and accepted risk. (author)

The approach to individual and collective risk in regard to radiation and its application to disposal of high level waste

International Nuclear Information System (INIS)

Snihs, J.O.

1994-01-01

In international and national criteria on disposal of HLW there are at present a number of requirements to the protection of individuals now and in the future. The protection of society (or environment) is directly or indirectly addressed in some criteria, but the number of people exposed, potentially exposed or at risk is not considered as a specific issue or quantity with constraints and implications. The report describes the various attitudes of society and its individuals towards the protection of the individual and the public. In particular, it treats how the number of people concerned by an irradiation situation influences the involvement of society in social and economic terms. Some conclusions can be drawn that are applicable to the situation of disposal of HLW. The discussion may illuminate the problems of disposal of HLW from some new angles and further the ambition of the society to present the disposal problems as broadly as possible. 23 refs

Unreviewed Disposal Question Evaluation: Waste Disposal in Engineered Trenches 3 and 4

Energy Technology Data Exchange (ETDEWEB)

Butcher, T. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Hamm, L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Flach, G. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2017-12-12

Revision 0 of this UDQE addressed the proposal to place Engineered Trench #3 (ET#3) in the footprint designated for Slit Trench #12 (ST#12) and operate using ST#12 disposal limits. Similarly, Revision 1 evaluates whether ET#4 can be located in and operated to Slit Trench #13 (ST#13) disposal limits. Both evaluations conclude that the proposed operations result in an acceptably small risk of exceeding a SOF of 1.0 and approve these actions from a performance assessment (PA) perspective. Because ET#3 will be placed in the location previously designated for ST#12, Solid Waste Management (SWM) requested that the Savannah River National Laboratory (SRNL) determine if the ST#12 limits could be employed as surrogate disposal limits for ET#3 operations. SRNL documented in this Unreviewed Disposal Question Evaluation (UDQE) that the use of ST#12 limits as surrogates for the new ET#3 disposal unit will provide reasonable assurance that Department of Energy (DOE) 435.1 performance objectives and measures (USDOE, 1999) will be protected. Therefore, new ET#3 inventory limits as determined by a Special Analysis (SA) are not required.

The management and disposal of sealed sources in France

International Nuclear Information System (INIS)

Drogou, A.

2005-01-01

The utilisation of sealed sources is very widespread in France, both in the medical and industrial fields. The rules for the management and retrieval of the sources are defined in the Decree of 4 April 2002. The principle of the retrieval of the sources is reliant on the supplier who is obliged to take back these sources. Financial guarantee systems have consequently been established to provide compensation for any failure by the supplier to take back the sources. The problems today in France are the absence of a disposal route and the management of the orphan sources. These have been integrated into the drawing up of the National Waste Management Plan (PNGDR) issued by the Minister for the Environment. Certain ideas and principles for the disposal of the sources have already been presented: Development of the principles of justification and recycling, development of disposal routes, development of a retrieval system for orphan sources; the importance of the establishment of financial guarantees for all the sources, the importance of consistency between the European regulations in order to have a simple return to the supplier in the case of imported sources. (author)

Geological disposal of nuclear waste

International Nuclear Information System (INIS)

1979-01-01

Fourteen papers dealing with disposal of high-level radioactive wastes are presented. These cover disposal in salt deposits, geologic deposits and marine disposal. Also included are papers on nuclear waste characterization, transport, waste processing technology, and safety analysis. All of these papers have been abstracted and indexed

The disposal of radioactive waste

International Nuclear Information System (INIS)

Ormai, P.

2006-01-01

The first part shows different ways of 'producing' radioactive wastes, defines the wastes of small, medium and high activity and gives estimation on the quantity of the necessary capacities of waste disposal facilities. The modern radioactive waste disposal that is the integrated processing of the form of waste, the package, the technical facility and the embedding geological environment that guarantee the isolation together. Another factor is the lifetime of radioactive waste which means that any waste containing long lifetime waste in higher concentration than 400-4000 kBq/kg should be disposed geologically. Today the centre of debate disposal of radioactive waste is more social than technical. For this reason not only geological conditions and technical preparations, but social discussions and accepting communities are needed in selecting place of facilities. Now, the focus is on long term temporary disposal of high activity wastes, like burnt out heating elements. The final part of the paper summarizes the current Hungarian situation of disposal of radioactive wastes. (T-R.A.)

Marine disposal of radioactive wastes - the debate

International Nuclear Information System (INIS)

Blair, I.

1985-01-01

The paper defends the case for marine disposal of radioactive wastes. The amount of packaged waste disposed; the site for marine disposal; the method of disposal; the radioactivity arising from the disposal; and safety factors; are all briefly discussed. (U.K.)

Ethical aspects in connection with the disposal of radioactive wastes

International Nuclear Information System (INIS)

Boetsch, W.

2003-01-01

The progress of modern natural and technological science and their far-reaching consequences affecting the distant future require increasingly practice-oriented ethical concepts. In the discussions about responseable acting, the question of the ethical tenability of nuclear energy nowadays takes a special position. Above all the problem of the disposal of radioactive wastes - the effects of which on the distant future have to be prognosticated - is controversially discussed in society. The Federal Ministry for the Environment, Nature Conservation and Nuclear Safety (BMU) commissioned Gesellschaft fuer Anlagen- und Reaktorsicherheit mbH (GRS) in the context of the project ''Disposal of radioactive wastes in the context of ethical objectives'' to summarise the current national and international status of ethical aspects in connection with the disposal of radioactive wastes. One aim of this report is to derive criteria to form the basis of a comprehensive discussion of the ethical aspects of the disposal of radioactive wastes. These criteria are to describe, as far as possible, all content-related aspects that result from radioactive waste disposal. The issues in this report resulting from the opinions, comments and publications presented are to serve as a basis for an experts' meeting at which the important ethical criteria concerning the responsible management of radioactive waste disposal are to be discussed at an interdisciplinary level with all those involved. The results of this report are based on an investigation which gathered the available national and international statements, principles, and criteria relating to the ethical aspects of the disposal of radioactive wastes and to sustainable development in the context of the technological impact assessment up to beginning of 2000. In the meantime, the debate in Germany has become somewhat more pragmatic, i. a. due to the work of the research group ''Arbeitskreis Auswahlverfahren Endlagerstandorte (AkEnd)'' and

Innovative Disposal Practices at the Nevada Test Site to Meet Its Low-Level Waste Generators' Future Disposal Needs

International Nuclear Information System (INIS)

Di Sanza, E.F.; Carilli, J.T.

2006-01-01

Low-level radioactive waste (LLW) streams which have a clear, defined pathway to disposal are becoming less common as U.S. Department of Energy accelerated cleanup sites enters their closure phase. These commonly disposed LLW waste streams are rapidly being disposed and the LLW inventory awaiting disposal is dwindling. However, more complex waste streams that have no path for disposal are now requiring attention. The U.S. Department of Energy (DOE) National Nuclear Security Administration Nevada Site Office (NSO) Environmental Management Program is charged with the responsibility of carrying out the disposal of onsite and off-site defense-generated and research-related LLW at the Nevada. Test Site (NTS). The NSO and its generator community are constantly pursuing new LLW disposal techniques while meeting the core mission of safe and cost-effective disposal that protects the worker, the public and the environment. From trenches to present-day super-cells, the NTS disposal techniques must change to meet the LLW generator's disposal needs. One of the many ways the NTS is addressing complex waste streams is by designing waste specific pits and trenches. This ensures unusual waste streams with high-activity or large packaging have a disposal path. Another option the NTS offers is disposal of classified low-level radioactive-contaminated material. In order to perform this function, the NTS has a safety plan in place as well as a secure facility. By doing this, the NTS can accept DOE generated classified low-level radioactive-contaminated material that would be equivalent to U.S. Nuclear Regulatory Commission Class B, C, and Greater than Class C waste. In fiscal year 2006, the NTS will be the only federal disposal facility that will be able to dispose mixed low-level radioactive waste (MLLW) streams. This is an activity that is highly anticipated by waste generators. In order for the NTS to accept MLLW, generators will have to meet the stringent requirements of the NTS

The chemistry of nuclear fuel waste disposal

International Nuclear Information System (INIS)

Wiles, D.R.

2002-01-01

About one-fifth of the world's supply of energy is derived from nuclear fission. While this important source of power avoids the environmental and resource problems of most other fuels, and although nuclear accident statistics are much less alarming, no other peacetime technology has evoked such public disquiet and impassioned feeling. Central to dealing with these fears is the management and disposal of radioactive waste. An expert Canadian panel in 1977 recommended permanent disposal of wastes in deep geological formations, providing a basis for subsequent policies and research. In 1988, the Federal Environmental Assessment Review Office (FEARO) appointed a panel to assess the proposed disposal concepts and to recommend government policy. The panel in turn appointed a Scientific Review Group to examine the underlying science. Behind all these issues lay one central question: How well is the chemistry understood? This became the principal concern of Professor Donald Wiles, the senior nuclear chemist of the Scientific Review Group. In this book, Dr. Wiles carefully describes the nature of radioactivity and of nuclear power and discusses in detail the management of radioactive waste by the multi-barrier system, but also takes an unusual approach to assessing the risks. Using knowledge of the chemical properties of the various radionuclides in spent fuel, this book follows each of the important radionuclides as it travels through the many barriers placed in its path. It turns out that only two radionuclides are able to reach the biosphere, and they arrive at the earth's surface only after many thousands of years. A careful analysis of the critical points of the disposal plan emphasizes site rejection criteria and other stages at which particular care must be taken, demonstrating how dangers can be anticipated and putting to rest the fear of nuclear fuel waste and its geological burial

Control and tracking arrangements for solid low-level waste disposals to the UK Drigg disposal site

International Nuclear Information System (INIS)

Elgie, K.G.; Grimwood, P.D.

1993-01-01

The Drigg disposal site has been the principal disposal site for solid low-level radioactive wastes (LLW) in the United Kingdom since 1959. It is situated on the Cumbrian coast, some six kilometers to the south of the Sellafield nuclear reprocessing site. The Drigg site receives LLW from a wide range of sources including nuclear power generation, nuclear fuel cycle activities, defense activities, isotope manufacture, universities, hospitals, general industry and clean-up of contaminated sites. This LLW has been disposed of in a series of trenches cut into the underlying clay layer of the site, and, since 1988, also into concrete lined vault. The total volume of LLW disposed of at Drigg is at present in the order of 800,000m 3 , with disposals currently approximately 25,000m 3 per year. British Nuclear Fuels plc (BNFL) owns and operates the Drigg disposal site. To meet operational and regulatory requirements, BNFL needs to ensure the acceptability of the disposed waste and be able to track it from its arising point to its specific disposal location. This paper describes the system that has been developed to meet these requirements

Problems in shallow land disposal of solid low-level radioactive waste in the united states

Science.gov (United States)

Stevens, P.R.; DeBuchananne, G.D.

1976-01-01

Disposal of solid low-level wastes containing radionuclides by burial in shallow trenches was initiated during World War II at several sites as a method of protecting personnel from radiation and isolating the radionuclides from the hydrosphere and biosphere. Today, there are 11 principal shallow-land burial sites in the United States that contain a total of more than 1.4 million cubic meters of solid wastes contaminated with a wide variety of radionuclides. Criteria for burial sites have been few and generalized and have contained only minimal hydrogeologic considerations. Waste-management practices have included the burial of small quantities of long-lived radionuclides with large volumes of wastes contaminated with shorter-lived nuclides at the same site, thereby requiring an assurance of extremely long-time containment for the entire disposal site. Studies at 4 of the 11 sites have documented the migration of radionuclides. Other sites are being studied for evidence of containment failure. Conditions at the 4 sites are summarized. In each documented instance of containment failure, ground water has probably been the medium of transport. Migrating radionuclides that have been identified include90Sr,137Cs,106Ru,239Pu,125Sb,60Co, and3H. Shallow land burial of solid wastes containing radionuclides can be a viable practice only if a specific site satisfies adequate hydrogeologic criteria. Suggested hydrogeologic criteria and the types of hydrogeologic data necessary for an adequate evaluation of proposed burial sites are given. It is mandatory that a concomitant inventory and classification be made of the longevity, and the physical and chemical form of the waste nuclides to be buried, in order that the anticipated waste types can be matched to the containment capability of the proposed sites. Ongoing field investigations at existing sites will provide data needed to improve containment at these sites and help develop hydrogeologic criteria for new sites. These

Near-surface land disposal

International Nuclear Information System (INIS)

Kittel, J.H.

1989-01-01

The Radioactive Waste Management Handbook provides a comprehensive, systematic treatment of nuclear waste management. Near-Surface Land Disposal, the first volume, is a primary and secondary reference for the technical community. To those unfamiliar with the field, it provides a bridge to a wealth of technical information, presenting the technology associated with the near-surface disposal of low or intermediate level wastes. Coverage ranges from incipient planning to site closure and subsequent monitoring. The book discusses the importance of a systems approach during the design of new disposal facilities so that performance objectives can be achieved; gives an overview of the radioactive wastes cosigned to near-surface disposal; addresses procedures for screening and selecting sites; and emphasizes the importance of characterizing sites and obtaining reliable geologic and hydrologic data. The planning essential to the development of particular sites (land acquisition, access, layout, surface water management, capital costs, etc.) is considered, and site operations (waste receiving, inspection, emplacement, closure, stabilization, etc.) are reviewed. In addition, the book presents concepts for improved confinement of waste, important aspects of establishing a monitoring program at the disposal facility, and corrective actions available after closure to minimize release. Two analytical techniques for evaluating alternative technologies are presented. Nontechnical issues surrounding disposal, including the difficulties of public acceptance are discussed. A glossary of technical terms is included

Disposal options for disused radioactive sources

International Nuclear Information System (INIS)

2005-01-01

This report presents a review of relevant information on the various technical factors and issues, as well as approaches and relevant technologies, leading to the identification of potential disposal options for disused radioactive sources. The report attempts to provide a logical 'road map' for the disposal of disused radioactive sources, taking into consideration the high degree of variability in the radiological properties of such types of radioactive waste. The use of borehole or shaft type repositories is highlighted as a potential disposal option, particularly for those countries that have limited resources and are looking for a simple, safe and cost effective solution for the disposal of their radioactive source inventories. It offers information about usage and characteristics of radioactive sources, disposal considerations, identification and screening of disposal options as well as waste packaging and acceptance criteria for disposal. The information provided in the report could be adapted or adopted to identify and develop specific disposal options suitable for the type and inventory of radioactive sources kept in storage in a given Member State

Disposal of tritium-exposed metal hydrides

International Nuclear Information System (INIS)

Nobile, A.; Motyka, T.

1991-01-01

A plan has been established for disposal of tritium-exposed metal hydrides used in Savannah River Site (SRS) tritium production or Materials Test Facility (MTF) R ampersand D operations. The recommended plan assumes that the first tritium-exposed metal hydrides will be disposed of after startup of the Solid Waste Disposal Facility (SWDF) Expansion Project in 1992, and thus the plan is consistent with the new disposal requiremkents that will be in effect for the SWDF Expansion Project. Process beds containing tritium-exposed metal hydride powder will be disposed of without removal of the powder from the bed; however, disposal of tritium-exposed metal hydride powder that has been removed from its process vessel is also addressed

Sub-seabed disposal of radioactive wastes

International Nuclear Information System (INIS)

Sivintsaev, Yu.V.

1990-01-01

The first stage of investigations of possibility of sub-seabed disposal of long-living intermediate-level radioactive wastes carried out by NIREX (UK) is described. Advantages and disadvantages of sub-seabed disposal of radioactive wastes are considered; regions suitable for disposal, transport means for marine disposal are described. Three types of sub-seabed burials are characterized

Co-disposal of sewage sludge and solid wastes-it works

Energy Technology Data Exchange (ETDEWEB)

Sussman, D B

1977-10-01

The problem of sludge disposal is one of more sludge than ever before, few suitable land disposal or land application sites, the ocean dumping option being phased out, and energy cost so high or supplies so few as to make incineration a questionable endeavor. The energy required to run a wastewater treatment plant and the heat needed to incinerate the sludge may be available in the same community in the form of municipal solid waste. Municipal sludge has a heat value of about 10,000 Btu/lb of dry solids; it is autogenous at>30% solids. Codisposal techniques are discussed which use the energy produced by the combustion of solid waste to dewater the sludge to its autogenous point. One approach is to use sewage sludge incinerators, in many cases already installed at the wastewater treatment plant, and to use the organic portion of solid waste as a fuel to dry, burn, and reduce the volume of the sludge that must ultimately be disposed. A second approach would use a solid waste incinerator, solid waste-fired steam generator, or waterwall combustion unit to burn dewatered sludge. Both approaches are being demonstrated or used. Thermal sludge disposal at wastewater treatment plants normally is carried out in multiple-hearth or fluidized-bed incinerators. The experiences of such plants in the US and Europe are summarized.

Assessment of concentration limit for the safe disposal of very low level wastes

International Nuclear Information System (INIS)

Nam, Yun Seog

2008-02-01

The large amounts of radionuclides are generated from the decommissioning of nuclear facilities (included the nuclear power plant). Because of this, countries or agencies using the nuclear power are one of considering issues for the effective disposal. Among decommissioning wastes, wastes have no or very limited radioactivity are disposed of in conventional landfill or recycled thought approval from regulatory control. And wastes like LILW (Low and Intermediate Level Wastes) or HLW (High Level Wastes) are sent the repository or the interim storage facilities. In order to solve the space problem of the LILW repository and reduce disposal costs, some LLW which are relatively lower than other LLW are classified as VLLW (Very Low Level Wastes). IAEA is added to the VLLW category of the radioactive waste classification and some countries are operating a VLLW disposal facility or will be operating. In this study, the VLLW acceptance criteria of each radionuclide are derived by considering the inadvertent human intrusion scenario applying to a study on the near-surface disposal (LILW). The effect of important parameter, especially, waste isolation period, dilution factor and food consumption rate, is considered. It is concluded that the concentration limits of radionuclides considering in this study are evaluated approximately between 1 and 100 Bq/g. These values are similar to the case of France and Spain and the IAEA's predicted values. Based on this study, acceptance criteria of VLLW disposal facilities are suggested. And this study is contributed to the public relations for the safety of the VLLW disposal facility

Radioactive waste disposal at Sellafield, UK: site selection, geological and engineering problems

International Nuclear Information System (INIS)

Haszeldine, R.S.; Smythe, D.K.

1996-01-01

UK Nirex is the company charged with finding a suitable site for the underground disposal of radioactive waste in the United Kingdom. Since 1991, Nirex has concentrated its investigation work at a site owned by British Nuclear Fuels Ltd near Sellafield. Planning permission was sought in 1994 for the development of an underground Rock Characterisation Facility at the site. A public Planning Inquiry began in September 1995. A wide range of scientific and technical objections were put by expert witnesses against the Nirex proposal. These witnesses were co-ordinated by three Objecting Organisations - Cumbria County Council, Friends of the Earth and Greenpeace. Their written evidence is presented in the 34 chapters of this book and separate abstracts have been written for each contribution. (UK)

High level radioactive wastes: Considerations on final disposal

International Nuclear Information System (INIS)

Ciallella, Norberto R.

2000-01-01

When at the beginnings of the decade of the 80 the National Commission on Atomic Energy (CNEA) in Argentina decided to study the destination of the high level radioactive wastes, was began many investigations, analysis and multidisciplinary evaluations that be origin to a study of characteristics never before carried out in Argentina. For the first time in the country was faced the study of an environmental eventual problem, several decades before that the problem was presented. The elimination of the high level radioactive wastes in the technological aspects was taken in advance, avoiding to transfer the problems to the future generations. The decision was based, not only in technical evaluations but also in ethical premises, since it was considered that the future generations may enjoy the benefits of the nuclear energy and not should be solve the problem. The CNEA in Argentina in 1980 decided to begin a feasibility study and preliminary engineering project for the construction of the final disposal of high level radioactive wastes

Municipal solid waste disposal in Portugal

International Nuclear Information System (INIS)

Magrinho, Alexandre; Didelet, Filipe; Semiao, Viriato

2006-01-01

In recent years municipal solid waste (MSW) disposal has been one of the most important environmental problems for all of the Portuguese regions. The basic principles of MSW management in Portugal are: (1) prevention or reduction, (2) reuse, (3) recovery (e.g., recycling, incineration with heat recovery), and (4) polluter-pay principle. A brief history of legislative trends in waste management is provided herein as background for current waste management and recycling activities. The paper also presents and discusses the municipal solid waste management in Portugal and is based primarily on a national inquiry carried out in 2003 and directed to the MSW management entities. Additionally, the MSW responsibility and management structure in Portugal is presented, together with the present situation of production, collection, recycling, treatment and elimination of MSW. Results showed that 96% of MSW was collected mixed (4% was separately collected) and that 68% was disposed of in landfill, 21% was incinerated at waste-to-energy plants, 8% was treated at organic waste recovery plants and 3% was delivered to sorting. The average generation rate of MSW was 1.32 kg/capita/day

PFR liquid metals disposal at Dounreay

International Nuclear Information System (INIS)

McIntyre, A.W.

1997-01-01

When the Prototype Fast Reactor (PFR) at Dounreay was shut down in 1994, the UKAEA commissioned a series of studies to determine the least cost, lowest risk option for dealing with the liquid metal coolants, i.e. the sodium from the primary and secondary circuits and the NaK from the decay heat removal system. The studies concluded that leaving the liquid metals in situ was not a viable option. Removing the liquid metals had three options, provision of long term external storage facilities, re-use in other projects or treatment for final disposal. The UKAEA invited companies to bid for the challenging task of disposing of more than 1500 t of liquid metals. In 1995 UKAEA awarded NNC Ltd. one of the largest decommissioning projects ever to be let competitively in the UK. During the first year of the contract, the challenges have focused on solving design problems and a number of innovative solutions have been developed by NNC and its subcontractors. From January 1997 the focus has moved to construction on site at Dounreay, and the manufacturing and installation of the mechanical components of the plant

Local Commune Administration as a Regulator of the Local Water Supply and Sewage Disposal Services Market

OpenAIRE

Małysko, Jacek

2012-01-01

In this article the author discusses problems related to the regulation of water and sewage disposal services market. In the beginning he describes the processes of water supply and sewage disposal taken by the local commune administration as a natural monopoly. Next he characterizes the structure of this market in Poland. Then he presents the role of local commune administration as a regulator. The author concludes by evaluating the existing Polish system of regulating wate...

Concept and problems on modernization of existing points for radioactive waste disposal in Belarus

International Nuclear Information System (INIS)

Zhemzhurov, Michail

1999-01-01

At present Belarus has no operating nuclear power plants (NPP) on its territory, the works with fissile materials carried out at the available nuclear and physical benches have been stopped. But not long ago a research reactor IRT-M with the capacity of 5000 kw was under operation from 1962 to 1986 at the Institute of Nuclear Power Engineering, now reorganized (located in Sosny settlement, 10 kilometers from Minsk-city), and a prototype of a small-sized mobile NPP with electric capacity of 630 kw was tested in 1985-1987, as well as a whole complex of nuclear and technical benches were into service, such as large-scale reactor loop plants for testing fuel elements and critical assemblies. About 1000 industrial, medical, scientific and research institutions use radioactive materials and the devices containing them in Belarus. Annually about 8000 kg of RAW and 6000 units of the spent sources of ionizing radiation (SIR) are generated by these enterprises which are to be obligatory disposed. Annual disposal of such RAW and SIR constitutes 10-50 tons with activity of 1-5).103 Ci. The paper presents the recommendations on extraction, reprocessing and conditioning of radioactive waste from the existing storages when PDWD reconstruction which have been developed with using the created computer database on the stored RAW

Sewage Sludge Disposal with Energy Recovery by Fluidized Bed Gasification and CHP-Units

Energy Technology Data Exchange (ETDEWEB)

Horst, J.; Gross, B.; Kimmerle, K. [Inst. fuer ZukunftsEnergieSysteme, Saarbruecken (Germany); Eder, C. [Christian Eder Technology e.K., Neunkirchen (Germany)

2006-07-15

Sewage sludge is a composition of by-products collected during the different stages of the waste water cleaning process of communal and industrial treatment plants. Because of its harmful impacts on environment as well as animals - and mankind - health sewage sludge has become a problem. Therefore disposal of sludge is today on a crossroad depending on the discussion about soil contamination by using the sludge as fertiliser. Some countries are now abandoning disposal to agriculture and are entering into thermal treatment with the argument: 'Harmful substances already separated with high financial effort should definitely be removed from the food cycle and should not return indirectly via the fields to food and water'. The SEDIS project - a project funded by the European Commission under the specific research and technological development programme 'Promotion of innovation and encouragement of SME participation' - is aimed at eliminating the rising disposal problem of sewage sludge by an energy-related use of the raw sludge directly on site of wastewater treatment plants. SEDIS is developing an innovative, self-sustaining system to process liquid and pasty waste such as sewage sludge and solid biomass to utilise product-gas for power-generation direct on site. This process is called ETVS-process and is patented by Christian Eder Technology e.K. Today, where each company has to look for sustainable savings, the SEDIS concept offers a decentralised process, self-sustaining from other energy sources and able to provide the whole treatment plant with energy. Furthermore the treatment plant would be independent of price policy of sludge disposers.

Financing of radioactive waste disposal

International Nuclear Information System (INIS)

Reich, J.

1989-01-01

Waste disposal is modelled as a financial calculus. In this connection the particularity is not primarily the dimension to be expected of financial requirement but above all the uncertainty of financial requirement as well as the ecological, socio-economic and especially also the temporal dimension of the Nuclear Waste Disposal project (disposal of spent fuel elements from light-water reactors with and without reprocessing, decommissioning = safe containment and disposal of nuclear power plants, permanent isolation of radioactive waste from the biosphere, intermediate storage). Based on the above mentioned factors the author analyses alternative approaches of financing or financial planning. He points out the decisive significance of the perception of risks or the evaluation of risks by involved or affected persons - i.e. the social acceptance of planned and designed waste disposal concepts - for the achievement and assessment of alternative solutions. With the help of an acceptance-specific risk measure developed on the basis of a mathematical chaos theory he illustrates, in a model, the social influence on the financing of nuclear waste disposal. (orig./HP) [de

Social dimensions of nuclear waste disposal

Energy Technology Data Exchange (ETDEWEB)

Grunwald, Armin [Karlsruhe Institute of Technology, Karlsruhe (Germany). Inst. for Technology Assessment and Systems Analysis

2015-07-01

Nuclear waste disposal is a two-faceted challenge: a scientific and technological endeavour, on the one hand, and confronted with social dimensions, on the other. In this paper I will sketch the respective social dimensions and will give a plea for interdisciplinary research approaches. Relevant social dimensions of nuclear waste disposal are concerning safety standards, the disposal 'philosophy', the process of determining the disposal site, and the operation of a waste disposal facility. Overall, cross-cutting issues of justice, responsibility, and fairness are of major importance in all of these fields.

Social dimensions of nuclear waste disposal

International Nuclear Information System (INIS)

Grunwald, Armin

2015-01-01

Nuclear waste disposal is a two-faceted challenge: a scientific and technological endeavour, on the one hand, and confronted with social dimensions, on the other. In this paper I will sketch the respective social dimensions and will give a plea for interdisciplinary research approaches. Relevant social dimensions of nuclear waste disposal are concerning safety standards, the disposal 'philosophy', the process of determining the disposal site, and the operation of a waste disposal facility. Overall, cross-cutting issues of justice, responsibility, and fairness are of major importance in all of these fields.

Recent Trends In The Methods Of Safety Assessment Of Rad Waste Treatment And Disposal

International Nuclear Information System (INIS)

Mahmoud, N.S.

2012-01-01

Radioactive waste management system involves a huge variety of processes and activities. This includes; collection and segregation, pretreatment, treatment, conditioning, storage and finally disposal. To assure the safety of the different facility of each step in the waste management system, the operator should prepare a safety analysis report to be assessed by the national regulatory body. The content of the safety analysis report must include all data about the site, facility design, operational phase, waste materials, and safety assessment methodologies. Safety assessment methodologies are iterative processes involving site-specific, prospective modeling evaluations of the pre-operational, operational, and post-closure time in case of disposal facilities. The safety assessment focuses primarily on a decision about compliance with performance objectives, rather than the much more difficult problem of predicting actual radiological impacts on the public at far future times. The recent organization processes of the safety assessment are improved by the ISAM working group from IAEA for waste disposal site. These safety assessment methodologies have been modified within SADRWMS IAEA project for the establishment of safety methodologies for the pre-disposal facilities (treatment and storage facilities) and the disposal site.

MethodS of radioactive waste processing and disposal in the United Kingdom

International Nuclear Information System (INIS)

Tolstykh, V.D.

1983-01-01

The results of investigations into radioactive waste processing and disposal in the United Kingdom are discussed. Methods for solidification of metal and graphite radioactive wastes and radioactive slime of the Magnox reactors are described. Specifications of different installations used for radioactive waste disposal are given. Climatic and geological conditions in the United Kingdom are such that any deep storages of wastes will be lower than the underground water level. That is why dissolution and transport by underground waters will inevitably result in radionuclide mobility. In this connection an extended program of investigations into the main three aspects of disposal problem namely radionucleide release in storages, underground water transport and radionuclide migration is realized. The program is divided in two parts. The first part deals with retrival of hydrological and geochemical data on geological formations, development of specialized methods of investigations which are necessary for identification of places for waste final disposal. The second part represents theoretical and laboratory investigations into provesses of radionuclide transport in the system of ''sttorage-geological formation''. It is concluded that vitrification on the base of borosilicate glass is the most advanced method of radioactive waste solidification

Some aspects of beryllium disposal in Kazakhstan

International Nuclear Information System (INIS)

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

2004-01-01

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

Technical responsibilities in low-level waste disposal

International Nuclear Information System (INIS)

Murray, R.L.; Walker, C.K.

1989-01-01

North Carolina will be the host state for a low-level radioactive waste (LLRW) disposal facility serving the Southeast Compact for 20 yr beginning in 1993. Primary responsibility for the project rests with the North Carolina Low-Level Radioactive Waste Management Authority, a citizen board. The North Carolina project embodies a unique combination of factors that places the authority in a position to exercise technical leadership in the LLRW disposal field. First, the Southeast Compact is the largest in the United States in terms of area, population, and waste generation. second, it is in a humid rather than an arid region. Third, the citizens of the state are intensely interested in preserving life style, environment, and attractiveness of the region to tourists and are especially sensitive to the presence of waste facilities of any kind. Finally, disposal rules set by the Radiation Protection Commission and enforced by the Radiation Protection Section are stricter than the U.S. Nuclear Regulatory Commission's 10CFR61. These four factors support the authority's belief that development of the facility cannot be based solely on engineering and economics, but that social factors, including perceptions of human risk, concerns for the environment, and opinions about the desirability of hosting a facility, should be integral to the project. This philosophy guides the project's many technical aspects, including site selection, site characterization, technology selection and facility design, performance assessment modeling, and waste reduction policies. Each aspect presents its own unique problems

Chemistry of nuclear waste disposal

International Nuclear Information System (INIS)

Zimmer, E.

1981-01-01

In extractive purification of the low-enriched uranium fuel element (UO 2 -particle fuel element with SiC coating) no problems arise in the PUREX-process which have not already been solved when reprocessing LWR-type reactor and breeder fuel elements. Concerning the HTR-type reactor fuel elements containing thorium, there are two process cycles behind the head end; the pure U-235 is reprocessed in the same manner as the low-enriched uranium fuel, and the thorium, which is the bigger fraction, is reprocessed together with U-233 in the same manner as the mixed oxides. Only the CO 2 -off gas system, which contains krypton and carbon 14, leads to difficulties in nuclear waste disposal. (DG) [de

Land disposal alternatives for low-level waste

International Nuclear Information System (INIS)

Alexander, P.; Lindeman, R.; Saulnier, G.; Adam, J.; Sutherland, A.; Gruhlke, J.; Hung, C.

1982-01-01

The objective of this project is to develop data regarding the effectiveness and costs of the following options for disposing of specific low-level nuclear waste streams; sanitary landfill; improved shallow land burial; intermediate depth disposal; deep well injection; conventional shallow land burial; engineered surface storage; deep geological disposal; and hydrofracturing. This will be accomplished through the following steps: (1) characterize the properties of the commercial low-level wastes requiring disposal; (2) evaluate the various options for disposing of this waste, characterize selected representative waste disposal sites and design storage facilities suitable for use at those sites; (3) calculate the effects of various waste disposal options on population health risks; (4) estimate the costs of various waste disposal options for specific sites; and (5) perform trade-off analyses of the benefits of various waste disposal options against the costs of implementing these options. These steps are described. 2 figures, 2 tables

Wildlife health implications of sewage disposal in wetlands

Science.gov (United States)

Friend, M.; Godfrey, P.J.; Kaynor, E.R.; Pelczarski, S.

1985-01-01

Wildlife health concerns associated with disposal of sewage effluent in wetlands are of three primary types: (1) introduction of pathogens, (2) introduction of pollutants that adversely impact on host body defense mechanisms, and (3) changes in the physical and chemical properties of wetlands that favor the development and maintenance of disease problems. Unlike the situation with human health concerns, introduction of pathogens is not the major concern regarding wildlife health. Instead, the focus of attention needs to be directed at environmental changes likely to take place as a result of effluent discharges into different types of wetlands. Unless these changes are adequately addressed from a disease perspective, marshes utilized for sewage disposal could become disease incubators and wildlife death traps. This result would be unfortunate because the backlash would likely negate the potentially beneficial aspects of the use of sewage wastewater for the creation of new wetlands and have a severe impact on progress being made towards evaluation of the compatibility of wildlife and sewage effluents.

Management, treatment and final disposal of solid hazardous hospital wastes

International Nuclear Information System (INIS)

Sebiani Serrano, T.

2000-01-01

Medical Waste is characterized by its high risk to human health and the environment. The main risk is biological, due to the large amount of biologically contaminated materials present in such waste. However, this does not mean that the chemical and radioactive wastes are less harmful just because they represent a smaller part of the total waste. Hazardous wastes from hospitals can be divided in 3 main categories: Solid Hazardous Hospital Wastes (S.H.H.W.), Liquid Hazardous Hospital Wastes (L.H.H.W.) and Gaseous Hazardous Hospital Wastes (G.H.H.W.) Most gaseous and liquid hazardous wastes are discharged to the environment without treatment. Since this inappropriate disposal practice, however, is not visible to society, there is no societal reaction to such problem. On the contrary, hazardous solid wastes (S.H.H.W.) are visible to society and create worries in the population. As a result, social and political pressures arise, asking for solutions to the disposal problems of such wastes. In response to such pressures and legislation approved by Costa Rica on waste handling and disposal, the Caja Costarricense de Seguro Social developed a plan for the handling, treatment, and disposal of hazardous solid wastes at the hospitals and clinics of its system. The objective of the program is to reduce the risk to society of such wastes. In this thesis a cost-effectiveness analysis was conducted to determine the minimum cost at which it is possible to reach a maximum level of reduction in hazardous wastes, transferring to the environment the least possible volume of solid hazardous wastes, and therefore, reducing risk to a minimum. It was found that at the National Children's Hospital the internal handling of hazard solid wastes is conducted with a high level of effectiveness. However, once out of the hospital area, the handling is not effective, because hazardous and common wastes are all mixed together creating a larger amount of S.H.H.W. and reducing the final efficiency

Unreviewed Disposal Question: A Discipline Process to Manage Change in LLW Disposal

International Nuclear Information System (INIS)

Goldston, W.T.

2000-01-01

The Department of Energy's waste management Order, DOE O 435.1, requires that low--level waste disposal facilities develop and maintain a radiological performance assessment to ensure that disposal operations are within a performance envelope defined by performance objectives for long-term protection of the public and the environment. The Order also requires that a radiological composite analysis be developed and maintained to ensure that the disposal facility, in combination with other sources of radioactive material that may remain when all DOE activities have ceased, will not compromise future radiological protection of the public and the environment. The Order further requires that a Disposal Authorization Statement (DAS) be obtained from DOE Headquarters and that the disposal facility be operated within the performance assessment, composite analysis, and DAS. Maintenance of the performance assessment and composite analysis includes conducting test, research, and monitoring activities to increase confidence in the results of the analyses. It also includes updating the analyses as changes are proposed in the disposal operations, or other information requiring an update, becomes available. Personnel at the Savannah River Site have developed and implemented an innovative process for reviewing proposed or discovered changes in low-level radioactive waste disposal operations. The process is a graded approach to determine, in a disciplined manner, whether changes are within the existing performance envelope, as defined by the performance assessment, composite analysis, and DAS, or whether additional analysis is required to authorize the change. This process is called the Unreviewed Disposal Question (UDQ) process. It has been developed to be analogous to the Unreviewed Safety Question (UDQ) process that has been in use within DOE for many years. This is the first formalized system implemented in the DOE complex to examine low-level waste disposal changes the way the

Hydrological balancing as applied to shallow ground disposal of radioactive wastes

International Nuclear Information System (INIS)

Kobera, P.; Dlouhy, Z.

1984-02-01

Shallow ground repositories are suitable disposal means for low and intermediate level radioactive wastes which offer an adequate form of containment of relatively short-lived radionuclides. The majority of safety related problems are connected with occurrence of water at the site. These problems include water accumulation in the disposal modules, high water table, hydrogeological complexity, water erosion, etc. In this context a simple technique is proposed for water balancing in the region of interest which would be relatively inexpensive and could supply large amounts of pertinent information. In the paper several balancing techniques based on water and/or energy balance methods are discussed. The results of a static evaluation of long term water balance averages are presented for the regions of planned shallow ground repositories near Dukovany and Mochovce in the CSSR. Hydrological processes and elements taking part in different hydrological cycles are treated from the dynamical point of view. The calculation methods for application of the kinematic approach are briefly touched. The results may be acquired at relatively low costs

Subseabed disposal safety analysis

International Nuclear Information System (INIS)

Koplick, C.M.; Kabele, T.J.

1982-01-01

This report summarizes the status of work performed by Analytic Sciences Corporation (TASC) in FY'81 on subseabed disposal safety analysis. Safety analysis for subseabed disposal is divided into two phases: pre-emplacement which includes all transportation, handling, and emplacement activities; and long-term (post-emplacement), which is concerned with the potential hazard after waste is safely emplaced. Details of TASC work in these two areas are provided in two technical reports. The work to date, while preliminary, supports the technical and environmental feasibility of subseabed disposal of HLW

Overview of nuclear waste disposal in space

International Nuclear Information System (INIS)

Rice, E.E.; Priest, C.C.

1981-01-01

One option receiving consideration by the Department of Energy (DOE) is the space disposal of certain high-level nuclear wastes. The National Aeronautics and Space Administration is assessing the space disposal option in support of DOE studies on alternatives for nuclear waste management. The space disposal option is viewed as a complement, since total disposal of fuel rods from commercial power plants is not considered to be economically practical with Space Shuttle technology. The space disposal of certain high-level wastes may, however, provide reduced calculated and perceived risks. The space disposal option in conjunction with terrestrial disposal may offer a more flexible and lower risk overall waste management system. For the space disposal option to be viable, it must be demonstrated that the overall long-term risks associated with this activity, as a complement to the mined geologic repository, would be significantly less than the long-term risk associated with disposing of all the high-level waste. The long-term risk benefit must be achieved within an acceptable short-term and overall program cost. This paper briefly describes space disposal alternatives, the space disposal destination, possible waste mixes and forms, systems and typical operations, and the energy and cost analysis

Site clean-up requirements: where does one dispose of dirt?

International Nuclear Information System (INIS)

Feldman, J.

1986-01-01

Under its Superfund program the US Environmental Protection Agency (EPA) has committed itself to remediate certain residential and commercial properties impacted by an accumulation of indoor radon or thoron resulting from deposition of contaminated dirt. A case in point: The State of New Jersey now has a number of sites contaminated with the residues of radium or thorium extraction operations. The residues (dirt) were removed from the original operations areas and used as landfill, often in locations which are now around houses or other buildings. EPA's soil contamination limits for radium or thorium dictate that remediation efforts consist of removal of that fill. This solution presents the problem of disposing of large volumes of marginally radioactive materials. Options which recognize the present lack of low-level radioactive waste disposal facilities are examined here

Safe disposal of research reactor RA spent fuel-activities, problems and prospects

International Nuclear Information System (INIS)

Matausek, M.V.; Vukadin, Z.; Plecas, I.; Pavlovic, R.; Sotic, O.; Bulkin, S.; Sokolov, A.; Morduhai, A.

2001-01-01

In order to improve conditions in the existing temporary spent fuel storage pool, technology was elaborated and equipment was produced and applied for removal of sludge and other debris from the bottom of the pool, filtration of the pool water, sludge conditioning in cement matrix and disposal at the low and medium waste repository at Vinca site. Safety measures and precautions were determined. Subcriticality was proved under normal and/or possible abnormal conditions. In the frame of the joint Yugoslav-Russian project, the technology has been developed and the equipment has been manufactured, tested and applied for underwater inspection the state of spent fuel inside the aluminum barrels. Based on the results of this inspection, a procedure will be proposed for transferring spent fuel to a more reliable storage facility. (author)

Preparation of heteropolyacid/TiO{sub 2}/fly-ash-cenosphere photocatalyst for the degradation of ciprofloxacin from aqueous solutions

Energy Technology Data Exchange (ETDEWEB)

Wu Di; Huo Pengwei; Lu Ziyang; Gao Xun [School of Chemistry and Chemical Engineering, Jiangsu University, Zhenjiang 212013 (China); Liu Xiaolin [School of Biology and Chemical Engineering, Jiangsu University of Science and Technology, Zhenjiang 212013 (China); Shi Weidong [School of Chemistry and Chemical Engineering, Jiangsu University, Zhenjiang 212013 (China); Yan Yongsheng, E-mail: huopw@ujs.edu.cn [School of Chemistry and Chemical Engineering, Jiangsu University, Zhenjiang 212013 (China)

2012-07-01

The TiO{sub 2}/fly-ash cenosphere photocatalysts modified with heteropolyacid were synthesized by sol-gel followed solvothermal method at 40 Degree-Sign C. Their chemical composition and optical absorption were characterized by X-ray diffraction (XRD), UV-vis diffuse reflectance spectra (UV-vis DRS), Fourier Transform Infra Red spectroscopy (FTIR) and Scanning electron microscopy (SEM). It was found that heteropolyacid modification could facilitate the absorption edge of TiO{sub 2}/fly-ash cenosphere photocatalyst to shift the visible light region. Heteropolyoxanion could be loaded on the titanium dioxide surface, by which could hinder the recombination rate of excited electron holes. The photocatalytic activity of TiO{sub 2}/fly-ash cenospheres modified with heteropolyacid was observed for the degradation of ciprofloxacin (CPFX) under visible light irradiation. The result from degradation of CPFX suggested that the photocatalytic activity of TiO{sub 2}/fly-ash cenospheres modified with silicotungstic acid was superior. The synergistic effects of heteropolyacid in modified TiO{sub 2}/fly-ash cenospheres photocatalyst particles were responsible for improving visible light photocatalytic activity. Besides, the novel photocatalyst was easy to recycle during post treatment because the fly-ash cenosphere was adopted for carrier.

A database for compliance with land disposal restrictions

International Nuclear Information System (INIS)

McCoy, M.W.

1990-09-01

The new restrictions on land disposal introduce additional challenges to hazardous waste managers. Laboratory waste streams consisting of small volumes of diverse waste types will be particularly difficult to manage due to the large number of possible treatment standards that could be applied. To help remedy this management problem, a user-friendly database has been developed to provide the regulatory information required for each of the hazardous wastes present in the wastes stream of a large research laboratory. 3 figs., 1 tab

HLW disposal dilemma

International Nuclear Information System (INIS)

Andrei, V.; Glodeanu, F.

2003-01-01

The radioactive waste is an inevitable residue from the use of radioactive materials in industry, research and medicine, and from the operation of generating electricity nuclear power stations. The management and disposal of such waste is therefore an issue relevant to almost all countries. Undoubtedly the biggest issue concerning radioactive waste management is that of high level waste. The long-lived nature of some types of radioactive wastes and the associated safety implications of disposal plans have raised concern amongst those who may be affected by such facilities. For these reasons the subject of radioactive waste management has taken on a high profile in many countries. Not one Member State in the European Union can say that their high level waste will be disposed of at a specific site. Nobody can say 'that is where it is going to go'. Now, there is a very broad consensus on the concept of geological disposal. The experts have little, if any doubt that we could safely dispose of the high level wastes. Large sectors of the public continue to oppose to most proposals concerning the siting of repositories. Given this, it is increasingly difficult to get political support, or even political decisions, on such sites. The failure to advance to the next step in the waste management process reinforces the public's initial suspicion and resistance. In turn, this makes the political decisions even harder. In turn, this makes the political decisions even harder. The management of spent fuel from nuclear power plant became a crucial issue, as the cooling pond of the Romanian NPP is reaching saturation. During the autumn of 2000, the plant owner proceeded with an international tendering process for the supply of a dry storage system to be implemented at the Cernavoda station to store the spent fuel from Unit 1 and eventually from Unit 2 for a minimum period of 50 years. The facility is now in operation. As concern the disposal of the spent fuel, the 'wait and see

Engineering geology of waste disposal

International Nuclear Information System (INIS)

Bentley, S.P.

1996-01-01

This volume covers a wide spectrum of activities in the field of waste disposal. These activities range from design of new landfills and containment properties of natural clays to investigation, hazard assessment and remediation of existing landfills. Consideration is given to design criteria for hard rock quarries when used for waste disposal. In addition, an entire section concerns the geotechnics of underground repositories. This covers such topics as deep drilling, in situ stress measurement, rock mass characterization, groundwater flows and barrier design. Engineering Geology of Waste Disposal examines, in detail, the active role of engineering geologists in the design of waste disposal facilities on UK and international projects. The book provides an authoritative mix of overviews and detailed case histories. The extensive spectrum of papers will be of practical value to those geologists, engineers and environmental scientists who are directly involved with waste disposal. (UK)

Waste Water Disposal Design And Management I

International Nuclear Information System (INIS)

Yang, Sang Hyeon; Lee, Jung Su

2004-04-01

This book gives descriptions of waste water disposal, design and management, which includes design of waterworks and sewerage facility such as preparatory work and building plan, used waste water disposal facilities, waste water disposal plant and industrial waste water disposal facilities, water use of waste water disposal plant and design of pump and pump facilities such as type and characteristic, selection and plan, screening and grit.

USA program on the waste disposal of nuclear military complexes

International Nuclear Information System (INIS)

Vinogradova, I.

1992-01-01

The USA program on the nuclear military complex waste disposal which focuses on the problems of environment protection and recovery is briefly considered. A group of works on the updating of the existing and on the construction of new nuclear weapon undustries is chosen to be the priority direction. The problem of radioactive waste burial in the Hunford nuclear complex is discussed. Total expenses for military enterprise purification from radioactive wastes are estimated as 91.2-129 billion dollars, and expenses for realization of the whole program are estimated as 180 billion dollars for 50 years

Costs for off-site disposal of nonhazardous oil field wastes: Salt caverns versus other disposal methods

Energy Technology Data Exchange (ETDEWEB)

Veil, J.A.

1997-09-01

According to an American Petroleum Institute production waste survey reported on by P.G. Wakim in 1987 and 1988, the exploration and production segment of the US oil and gas industry generated more than 360 million barrels (bbl) of drilling wastes, more than 20 billion bbl of produced water, and nearly 12 million bbl of associated wastes in 1985. Current exploration and production activities are believed to be generating comparable quantities of these oil field wastes. Wakim estimates that 28% of drilling wastes, less than 2% of produced water, and 52% of associated wastes are disposed of in off-site commercial facilities. In recent years, interest in disposing of oil field wastes in solution-mined salt caverns has been growing. This report provides information on the availability of commercial disposal companies in oil-and gas-producing states, the treatment and disposal methods they employ, and the amounts they charge. It also compares cavern disposal costs with the costs of other forms of waste disposal.

Hazardous Waste Development, Demonstration, and Disposal (HAZWDDD) program plan: Executive summary

International Nuclear Information System (INIS)

McGinnis, C.P.; Eisenhower, B.M.; Reeves, M.E.; DePaoli, S.M.; Stinton, L.H.; Harrington, E.H.

1989-02-01

The Hazardous Waste Development, Demonstration, and Disposal (HAZWDDD) Program Plan provides a strategy for management of hazardous and mixed wastes generated by the five Department of Energy (DOE) installations managed by Martin Marietta Energy Systems, Inc. (Energy Systems). This integrated corporate plan is based on the individual installation plans, which identify waste streams, facility capabilities, problem wastes, future needs, and funding needs. Using this information, the corporate plan identifies common concerns and technology/facility needs over the next 10 years. The overall objective of this corporate plan is to ensure that treatment, storage, and disposal (TSD) needs for all hazardous and mixed wastes generated by Energy Systems installations have been identified and planned for. Specific objectives of the program plan are to (1) identify all hazardous and mixed waste streams; (2) identify hazardous and mixed waste TSD requirements; (3) identify any unresolved technical issues preventing implementation of the strategy; (4) develop schedules for studies, demonstrations, and facilities to resolve the issues; and (5) define the interfaces with the Low-Level Waste Disposal Development and Demonstration (LLWDDD) Program. 10 refs., 7 figs

EVALUATION OF TIRE RUBBER DISPOSAL IN CONCRETE FOR PAVEMENTS

Directory of Open Access Journals (Sweden)

Rosa Cristina Cecche Lintz

2009-01-01

Full Text Available The production of waste by the tire industry has been a growing problem, indicating the need for its reuse. More than thirty million tires are discharged per year in Brazil, where regulation for the environment states that for each four new tires, five unusable ones must be adequately disposed by manufacturers and importers. Paving consumes an extremely large quantity of materials, which can be the source of rational application of waste and rejected materials. Research shows that tire rubber can be added to asphalt, which increases its durability and improves pavement quality and safety conditions by absorbing the rubber elastic properties, and also be used for architectural applications, among others. This study deals with the addition of rubber fibers from tire crushing in concrete for roadway pavements in order to provide proper indication about the alternative material disposal through an evaluation of the mechanical behavior of the modified concrete. Different concrete mixes were produced, within which, part of fine aggregates were substituted by tire rubber and mechanical experiment tests were performed, which show that, due to great resistance losses, the disposal of this alternative material in concrete should be considered for light traffic pavements, with the addition of rubber ranging up to 10% in mass.

EVALUATION OF TIRE RUBBER DISPOSAL IN CONCRETE FOR PAVEMENTS

Directory of Open Access Journals (Sweden)

Rosa Cristina Cecche Lintz

2009-12-01

Full Text Available The production of waste by the tire industry has been a growing problem, indicating the need for its reuse. More than thirty million tires are discharged per year in Brazil, where regulation for the environment states that for each four new tires, five unusable ones must be adequately disposed by manufacturers and importers. Paving consumes an extremely large quantity of materials, which can be the source of rational application of waste and rejected materials. Research shows that tire rubber can be added to asphalt, which increases its durability and improves pavement quality and safety conditions by absorbing the rubber elastic properties, and also be used for architectural applications, among others. This study deals with the addition of rubber fibers from tire crushing in concrete for roadway pavements in order to provide proper indication about the alternative material disposal through an evaluation of the mechanical behavior of the modified concrete. Different concrete mixes were produced, within which, part of fine aggregates were substituted by tire rubber and mechanical experiment tests were performed, which show that, due to great resistance losses, the disposal of this alternative material in concrete should be considered for light traffic pavements, with the addition of rubber ranging up to 10% in mass.

Efficiency analyses of the CANDU spent fuel repository using modified disposal canisters for a deep geological disposal system design

International Nuclear Information System (INIS)

Lee, J.Y.; Cho, D.K.; Lee, M.S.; Kook, D.H.; Choi, H.J.; Choi, J.W.; Wang, L.M.

2012-01-01

Highlights: ► A reference disposal concept for spent nuclear fuels in Korea has been reviewed. ► To enhance the disposal efficiency, alternative disposal concepts were developed. ► Thermal analyses for alternative disposal concepts were performed. ► From the result of the analyses, the disposal efficiency of the concepts was reviewed. ► The most effective concept was suggested. - Abstract: Deep geological disposal concept is considered to be the most preferable for isolating high-level radioactive waste (HLW), including nuclear spent fuels, from the biosphere in a safe manner. The purpose of deep geological disposal of HLW is to isolate radioactive waste and to inhibit its release of for a long time, so that its toxicity does not affect the human beings and the biosphere. One of the most important requirements of HLW repository design for a deep geological disposal system is to keep the buffer temperature below 100 °C in order to maintain the integrity of the engineered barrier system. In this study, a reference disposal concept for spent nuclear fuels in Korea has been reviewed, and based on this concept, efficient alternative concepts that consider modified CANDU spent fuels disposal canister, were developed. To meet the thermal requirement of the disposal system, the spacing of the disposal tunnels and that of the disposal pits for each alternative concept, were drawn following heat transfer analyses. From the result of the thermal analyses, the disposal efficiency of the alternative concepts was reviewed and the most effective concept suggested. The results of these analyses can be used for a deep geological repository design and detailed analyses, based on exact site characteristics data, will reduce the uncertainty of the results.

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

International Nuclear Information System (INIS)

2015-01-01

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

Update on the Federal Facilities Compliance Act disposal workgroup disposal site evaluation - what has worked and what has not

International Nuclear Information System (INIS)

Case, J.T.; Waters, R.D.

1995-01-01

The Department of Energy (DOE) has been developing a planning process for mixed low-level waste (MLLW) disposal in conjunction with the affected states for over two years and has screened the potential disposal sites from 49 to 15. A radiological performance evaluation was conducted on these fifteen sites to further identify their strengths and weaknesses for disposal of MLLW. Technical analyses are on-going. The disposal evaluation process has sufficiently satisfied the affected states' concerns to the point that disposal has not been a major issue in the consent order process for site treatment plans. Additionally, a large amount of technical and institutional information on several DOE sites has been summarized. The relative technical capabilities of the remaining fifteen sites have been demonstrated, and the benefits of waste form and disposal facility performance have been quantified. However, the final disposal configuration has not yet been determined. Additionally, the MLLW disposal planning efforts will need to integrate more closely with the low-level waste disposal activities before a final MLLW disposal configuration can be determined. Recent Environmental Protection Agency efforts related to the definition of hazardous wastes may also affect the process

Modeling long-term aspects of nuclear waste disposal: the AEGIS experience

International Nuclear Information System (INIS)

Dove, F.H.

1983-01-01

Modeling the long-term aspects of nuclear waste disposal has its roots in risk analysis of man-made systems like nuclear reactors. Analytical problems can be introduced into the performance assessment of a site-specific repository if an appreciation for the behavior of a natural earth system is not maintained. However, this should not preclude the application of historically useful analytical techniques like bounding strategies in favor of emerging, data-intensive techniques. The technical challenge is to apply existing technology and available data to a complex problem and produce a useful result

Radioactive waste disposal

International Nuclear Information System (INIS)

Cluchet, J.; Roger, B.

1975-10-01

After mentioning the importance of the problem of the disposal of wastes produced in the electro-nuclear industry, a short reminder on a few laws of radioactivity (nature and energy of radiations, half-life) and on some basic dosimetry is given. The conditioning and storage procedures are then indicated for solid wastes. The more active fractions of liquid wastes are incorporated into blocks of glass, whereas the less active are first concentrated by chemical treatments or by evaporation. The concentrates are then embedded into concrete, asphalt or resins. Storage is done according to the nature of each type of wastes: on a hard-surfaced area or inside concrete-lined trenches for the lowest radioactivity, in pits for the others. Transuranium elements with very long half-lives are buried in very deep natural cavities which can shelter them for centuries. From the investigations conducted so far and from the experience already gained, it can be concluded that safe solutions are within our reach [fr

Generalized economic model for evaluating disposal costs at a low-level waste disposal facility

International Nuclear Information System (INIS)

Baird, R.D.; Rogers, V.C.

1985-01-01

An economic model is developed which can be used to evaluate cash flows associated with the development, operations, closure, and long-term maintenance of a proposed Low-Level Radioactive Waste disposal facility and to determine the unit disposal charges and unit surcharges which might result. The model includes the effects of nominal interest rate (rate of return on investment, or cost of capital), inflation rate, waste volume growth rate, site capacity, duration of various phases of the facility history, and the cash flows associated with each phase. The model uses standard discounted cash flow techniques on an after-tax basis to determine that unit disposal charge which is necessary to cover all costs and expenses and to generate an adequate rate of return on investment. It separately considers cash flows associated with post-operational activities to determine the required unit surcharge. The model is applied to three reference facilities to determine the respective unit disposal charges and unit surcharges, with various values of parameters. The sensitivity of the model results are evaluated for the unit disposal charge

Development of groundwater flow modeling for the low-level radwaste disposal (I)

Energy Technology Data Exchange (ETDEWEB)

Bae, Dae Seok; Kim, Chun Soo; Kim, Kyung Soo; Koh, Yong Kweon; Hwang, Yong Soo; Park, Hyun Soo [Korea Atomic Energy Research Institute, Taejon (Korea)

1999-08-01

Major problems facing in the hydrogeological assessment for a disposal site are resulted from the uncertainties involved in hydraulic parameters of geologic media and the limitation of field investigation methods. These technical problems are, in turn, closely related to the confidence level of numerical modeling results. This research project aims to establish the hydrogeologic assessment methodology suitable to domestic geologic environments with reference to the safety analysis and site characterization for a repository. 26 refs., 65 figs., 14 tabs. (Author)

Micro-organisms and nuclear waste: a neglected problem

International Nuclear Information System (INIS)

Arnott, Don.

1989-01-01

The paper addresses the problem of bacteria in nuclear waste disposal. A description is given of how bacteria colonised the Three Mile Island Nuclear Reactor soon after meltdown, demonstrating the ability of some bacteria to operate under extreme conditions. Work is also described indicating that microbial corrosion of metal canisters can occur. Thus the author recommends that studies of nuclear waste disposal should take into account the interrelations between geology, geochemistry and microbiology. (U.K.)

The uncertain future for nuclear graphite disposal: Crisis or opportunity?

International Nuclear Information System (INIS)

Wickham, A.J.; Neighbour, G.B.; Dubourg, M.

2001-01-01

to be retained in interim surface storage. It appears to the authors to be an appropriate time to review the situation closely and to consider the problem entirely on the basis of established scientific fact and a comparative risk analysis, unfettered by the perceived political constraints to which the nuclear operators and decommissioning organisations are necessarily subjected. This paper seeks to raise again for scientific debate all of these possibilities for graphite disposal, without prejudice necessarily to political constraints, in order to try to focus on genuinely the most satisfactory outcome to all concerned. (author)

Integration tendencies and potential of North in problem of radioactive waste isolation

International Nuclear Information System (INIS)

Komlev, V.N.; Bichuk, N.I.; Zajtsev, V.G.; Melikhova, G.S.; Pavlov, V.A.

2001-01-01

Problems of underground solid radioactive waste disposal construction in Kola peninsula (Russian Federation) are considered. Several disposal sites are proposed. Special NUCRUS 95410 project was created in 1996 which reflects complex comparative investigations of the most prospective sites. Economic, political, social and scientific aspects are studied

Disposal of radioactive waste material

International Nuclear Information System (INIS)

Cairns, W.J.; Burton, W.R.

1984-01-01

A method of disposal of radioactive waste consists in disposing the waste in trenches dredged in the sea bed beneath shallow coastal waters. Advantageously selection of the sites for the trenches is governed by the ability of the trenches naturally to fill with silt after disposal. Furthermore, this natural filling can be supplemented by physical filling of the trenches with a blend of absorber for radionuclides and natural boulders. (author)

Soil homogeneity evaluation by radionuclide tracer breakthrough curve interpretation

International Nuclear Information System (INIS)

Brenizer, J.S. Jr.; Jarrett, A.R.; Jester, W.A.

1980-01-01

Increasing concern about the environmental impact of hazardous waste disposal has made site evaluation and site selection difficult and expensive. Pollutants, assumed to be absorbed by the soil immediately surrounding the burial trench, have been detected far from sites. Discrepancies between predicted migration distances based on indirect methods such as laboratory and computer modeling and those observed at the field site are often significant. The homogeneity of subsurface media, often assumed in laboratory and modeling studies, is seldom found in the field. The use of tracers to determine the flow characteristics of a potential disposal site involves time and expense, but offers a direct evaluation of solute transport and eliminates the assumptions inherent in indirect methods. Current modeling of solute transport in nonhomogeneous porous media is limited by the quantification of input parameters. Several general models can predict solute transport in saturated-unsaturated media from low-level disposal sites if the hydraulic characteristics and chemical reactions expected in each unique water-solute-media system can be defined. The objective of this research was to develop a method of evaluating potential shallow-land burial waste disposal sites by interpreting tracer breakthrough curve structure with respect to the hydrologic properties of the media at the potential disposal site. This methodology will be helpful in evaluating the potential performance of many types of shallow-land waste burial sites such as low-level radioactive waste disposal, surface disposal of flyash, chemical waste disposal, waste sedimentation ponds, and sanitary landfills

48 CFR 2845.603 - Disposal methods.

Science.gov (United States)

2010-10-01

... 48 Federal Acquisition Regulations System 6 2010-10-01 2010-10-01 true Disposal methods. 2845.603 Section 2845.603 Federal Acquisition Regulations System DEPARTMENT OF JUSTICE Contract Management GOVERNMENT PROPERTY Reporting, Redistribution, and Disposal of Contractor Inventory 2845.603 Disposal methods...

48 CFR 945.603 - Disposal methods.

Science.gov (United States)

2010-10-01

... 48 Federal Acquisition Regulations System 5 2010-10-01 2010-10-01 false Disposal methods. 945.603 Section 945.603 Federal Acquisition Regulations System DEPARTMENT OF ENERGY CONTRACT MANAGEMENT GOVERNMENT PROPERTY Reporting, Redistribution, and Disposal of Contractor Inventory 945.603 Disposal methods. ...

Low-level waste disposal site performance assessment with the RQ/PQ methodology. Final report

International Nuclear Information System (INIS)

Rogers, V.C.; Grant, M.W.; Sutherland, A.A.

1982-12-01

A methodology called RQ/PQ (retention quotient/performance quotient) has been developed for relating the potential hazard of radioactive waste to the natural and man-made barriers provided by a disposal facility. The methodology utilizes a systems approach to quantify the safety of low-level waste disposed in a near-surface facility. The main advantages of the RQ/PQ methodology are its simplicity of analysis and clarity of presentation while still allowing a comprehensive set of nuclides and pathways to be treated. Site performance and facility designs for low-level waste disposal can be easily investigated with relatively few parameters needed to define the problem. Application of the methodology has revealed that the key factor affecting the safety of low-level waste disposal in near surface facilities is the potential for intrusion events. Food, inhalation and well water pathways dominate in the analysis of such events. While the food and inhalation pathways are not strongly site-dependent, the well water pathway is. Finally, burial at depths of 5 m or more was shown to reduce the impacts from intrusion events

Radioactive waste disposal implications of extending Part IIA of the Environmental Protection Act to cover radioactively contaminated land.

Science.gov (United States)

Nancarrow, D J; White, M M

2004-03-01

A short study has been carried out of the potential radioactive waste disposal issues associated with the proposed extension of Part IIA of the Environmental Protection Act 1990 to include radioactively contaminated land, where there is no other suitable existing legislation. It was found that there is likely to be an availability problem with respect to disposal at landfills of the radioactive wastes arising from remediation. This is expected to be principally wastes of high volume and low activity (categorised as low level waste (LLW) and very low level waste (VLLW)). The availability problem results from a lack of applications by landfill operators for authorisation to accept LLW wastes for disposal. This is apparently due to perceived adverse publicity associated with the consultation process for authorisation coupled with uncertainty over future liabilities. Disposal of waste as VLLW is limited both by questions over volumes that may be acceptable and, more fundamentally, by the likely alpha activity of wastes (originating from radium and thorium operations). Authorised on-site disposal has had little attention in policy and guidance in recent years, but may have a part to play, especially if considered commercially attractive. Disposal at BNFL's near surface disposal facility for LLW at Drigg is limited to wastes for which there are no practical alternative disposal options (and preference has been given to operational type wastes). Therefore, wastes from the radioactively contaminated land (RCL) regime are not obviously attractive for disposal to Drigg. Illustrative calculations have been performed based on possible volumes and activities of RCL arisings (and assuming Drigg's future volumetric disposal capacity is 950,000 m3). These suggest that wastes arising from implementing the RCL regime, if all disposed to Drigg, would not represent a significant fraction of the volumetric capacity of Drigg, but could have a significant impact on the radiological

Radioactive waste disposal implications of extending Part IIA of the Environmental Protection Act to cover radioactively contaminated land

International Nuclear Information System (INIS)

Nancarrow, D J; White, M M

2004-01-01

A short study has been carried out of the potential radioactive waste disposal issues associated with the proposed extension of Part IIA of the Environmental Protection Act 1990 to include radioactively contaminated land, where there is no other suitable existing legislation. It was found that there is likely to be an availability problem with respect to disposal at landfills of the radioactive wastes arising from remediation. This is expected to be principally wastes of high volume and low activity (categorised as low level waste (LLW) and very low level waste (VLLW)). The availability problem results from a lack of applications by landfill operators for authorisation to accept LLW wastes for disposal. This is apparently due to perceived adverse publicity associated with the consultation process for authorisation coupled with uncertainty over future liabilities. Disposal of waste as VLLW is limited both by questions over volumes that may be acceptable and, more fundamentally, by the likely alpha activity of wastes (originating from radium and thorium operations). Authorised on-site disposal has had little attention in policy and guidance in recent years, but may have a part to play, especially if considered commercially attractive. Disposal at BNFL's near surface disposal facility for LLW at Drigg is limited to wastes for which there are no practical alternative disposal options (and preference has been given to operational type wastes). Therefore, wastes from the radioactively contaminated land (RCL) regime are not obviously attractive for disposal to Drigg. Illustrative calculations have been performed based on possible volumes and activities of RCL arisings (and assuming Drigg's future volumetric disposal capacity is 950 000 m 3 ). These suggest that wastes arising from implementing the RCL regime, if all disposed to Drigg, would not represent a significant fraction of the volumetric capacity of Drigg, but could have a significant impact on the radiological

Criteria and techniques for field characterization and modeling related to selecting and evaluating performance of LILW disposal sites

International Nuclear Information System (INIS)

Faybishenko, Boris; Witherspoon, Paul A.

2007-01-01

Argentina is faced with the challenging problem of developing technology for near-surface disposal and isolation of low- and intermediate-level radioactive waste (LILW). The preferred option for disposal of LILW (including both relatively short-lived and long-lived radionuclides) is to use disposal facilities that are near-surface--either above or below ground level [IAEA, 1985; 2001a;2004]. How individual components of a waste disposal system perform (including waste forms, waste containers, engineered barriers and host environment) will determine system safety and the safety of the surrounding environment [IAEA, 1999]. The lack of appropriate engineering for the backfill, and for the selection of sealing and covering materials for trenches, vaults, and ditches, could result in the escape of radionuclides from the disposed wastes [IAEA, 1994a; 2001b]. Therefore, assessment and design of backfill, barriers, and cover materials are very important, both for preventing invasion of water into the disposal system, and for retarding radionuclides that could potentially migrate from the system into the atmosphere or groundwater [IAEA, 1982; 1994b;2001a

Safety of direct disposal of spent fuel and of disposal of reprocessing waste

Energy Technology Data Exchange (ETDEWEB)

Besnus, F. [Institut de Radioprotection et de Surete Nucleaire (IRSN), 92 - Fontenay-aux-Roses (France)

2006-07-01

In 2005, the French Agency for Radioactive waste management (ANDRA) established a report on the feasibility of the geological disposal of high level and intermediate level long lived radioactive waste, in a clay formation. The hypothesis of spent fuel direct disposal was also considered. By the end of 2005, IRSN performed a complete technical review of ANDRA's report, aiming at highlighting the salient safety issues that were to be addressed within a process that may possibly lead to the creation of a disposal facility for these wastes. The following publication presents the main conclusions of this technical review. (author)

Safety of direct disposal of spent fuel and of disposal of reprocessing waste

International Nuclear Information System (INIS)

Besnus, F.

2006-01-01

In 2005, the French Agency for Radioactive waste management (ANDRA) established a report on the feasibility of the geological disposal of high level and intermediate level long lived radioactive waste, in a clay formation. The hypothesis of spent fuel direct disposal was also considered. By the end of 2005, IRSN performed a complete technical review of ANDRA's report, aiming at highlighting the salient safety issues that were to be addressed within a process that may possibly lead to the creation of a disposal facility for these wastes. The following publication presents the main conclusions of this technical review. (author)

Treatment of uncertainties in the geologic disposal of radioactive waste

International Nuclear Information System (INIS)

Cranwell, R.M.

1985-01-01

Uncertainty in the analysis of geologic waste disposal is generally considered to have three primary components: (1) computer code/model uncertainty, (2) model parameter uncertainty, and (3) scenario uncertainty. Computer code/model uncertainty arises from problems associated with determination of appropriate parameters for use in model construction, mathematical formulatin of models, and numerical techniques used in conjunction with the mathematical formulation of models. Model parameter uncertainty arises from problems associated with selection of appropriate values for model input, data interpretation and possible misuse of data, and variation of data. Scenario uncertainty arises from problems associated with the ''completeness' of scenarios, the definition of parameters which describe scenarios, and the rate or probability of scenario occurrence. The preceding sources of uncertainty are discussed below

Regulatory decision making in the presence of uncertainty in the context of the disposal of long lived radioactive wastes. Third report of the Working group on principles and criteria for radioactive waste disposal

International Nuclear Information System (INIS)

1997-10-01

Plans for disposing of radioactive wastes have raised a number of unique and mostly philosophical problems, mainly due to the very long time-scales which have to be considered. While there is general agreement on disposal concepts and on many aspects of a safety philosophy, consensus on a number of issues remains to be achieved. The IAEA established a subgroup under the International Radioactive Waste Management Advisory Committee (INWAC). The subgroup started its work in 1991 as the ''INWAC Subgroup on Principles and Criteria for Radioactive Waste Disposal''. With the reorganization in 1995 of IAEA senior advisory committees in the nuclear safety area, the title of the group was changed to ''Working Group on Principles and Criteria for Radioactive Waste Disposal''. The working group is intended to provide an open forum for: (1) the discussion and resolution of contentious issues, especially those with an international component, in the area of principles and criteria for safe disposal of waste; (2) the review and analysis of new ideas and concepts in the subject area; (3) establishing areas of consensus; (4) the consideration of issues related to safety principles and criteria in the IAEA's Radioactive Waste Safety Standards (RADWASS) programme; (5) the exchange of information on national safety criteria and policies for radioactive waste disposal. This is the third report of the working group and it deals with the subject of regulatory decision making under conditions of uncertainty which is a matter of concern with respect to disposal of radioactive wastes underground. 14 refs

Basic concept on safety regulation for land disposal of low level radioactive solid wastes

International Nuclear Information System (INIS)

1985-01-01

As to the land disposal of low level radioactive solid wastes, to which the countermeasures have become the urgent problem at present, it is considered to be a realistic method to finally store the solid wastes concentratedly outside the sites of nuclear power stations and others, and effort has been exerted by those concerned to realize it. Besides, as for extremely low level radioactive solid wastes, the measures of disposing them corresponding to the radioactivity level are necessary, and the concrete method has been examined. The Committee on Safety Regulation for Radioactive Wastes has discussed the safety regulation for those since April, 1984, and the basic concept on the safety regulation was worked up. It is expected that the safety of the land disposal of low level radioactive solid wastes can be ensured when the safety regulation is carried out in conformity with this basic concept. The present status of the countermeasures to the land disposal of low level radioactive solid wastes is shown. As the concrete method, the disposal in shallow strate has been generally adopted. At present, the plan for the final storage in Aomori Prefecture is considered, and it will be started with the first stage of four-stage control. (Kako, I.)

International safeguards relevant to geologic disposal of high-level wastes and spent fuels

International Nuclear Information System (INIS)

Pillay, K.K.S.; Picard, R.R.

1989-01-01

Spent fuels from once-through fuel cycles placed in underground repositories have the potential to become attractive targets for diversion and/or theft because of their valuable material content and decreasing radioactivity. The first geologic repository in the US, as currently designed, will contain approximately 500 Mt of plutonium, 60,000 Mt of uranium and a host of other fissile and strategically important elements. This paper identifies some of the international safeguards issues relevant to the various proposed scenarios for disposing of the spent fuel. In the context of the US program for geologic disposal of spent fuels, this paper highlights several issues that should be addressed in the near term by US industries, the Department of Energy, and the Nuclear Regulatory Commission before the geologic repositories for spent fuels become a reality. Based on US spent fuel discharges, an example is presented to illustrate the enormity of the problem of verifying spent fuel inventories. The geologic disposal scenario for high-level wastes originating from defense facilities produced a ''practicably irrecoverable'' waste form. Therefore, safeguards issues for geologic disposal of high-level waste now in the US are less pressing. 56 refs. , 2 figs

An Optimization Approach for Hazardous Waste Management Problem under Stochastic Programming

International Nuclear Information System (INIS)

Abass, S.A.; Abdallah, A.S.; Gomaa, M.A.

2008-01-01

Hazardous waste is the waste which, due to their nature and quantity, is potentially hazardous to human health and/or the environment. This kind of waste requires special disposal techniques to eliminate or reduce thc hazardous. Hazardous waste management (HWM) problem is concerned in the basic with the disposal method. hi this paper we focus on incineration as an effective to dispose the waste. For this type of disposal, there arc air pollution standards imposed by the government. We will propose an optimization model satisfied the air pollution standards and based on the model of Emek and Kara with using random variable coefficients in the constraint

Iraq nuclear facility dismantlement and disposal project

Energy Technology Data Exchange (ETDEWEB)

Cochran, J R; Danneels, J [Sandia National Laboratories, Albuquerque, NM (United States); Kenagy, W D [U.S. Department of State, Bureau of International Security and Nonproliferation, Office of Nuclear Energy, Safety and Security, Washington, DC (United States); Phillips, C J; Chesser, R K [Center for Environmental Radiation Studies, Texas Tech University, Lubbock, TX (United States)

2007-07-01

The Al Tuwaitha nuclear complex near Baghdad contains a significant number of nuclear facilities from Saddam Hussein's dictatorship. Because of past military operations, lack of upkeep and looting there is now an enormous radioactive waste problem at Al Tuwaitha. Al Tuwaitha contains uncharacterised radioactive wastes, yellow cake, sealed radioactive sources, and contaminated metals. The current security situation in Iraq hampers all aspects of radioactive waste management. Further, Iraq has never had a radioactive waste disposal facility, which means that ever increasing quantities of radioactive waste and material must be held in guarded storage. The Iraq Nuclear Facility Dismantlement and Disposal Program (the NDs Program) has been initiated by the U.S. Department of State (DOS) to assist the Government of Iraq (GOI) in eliminating the threats from poorly controlled radioactive materials, while building human capacities so that the GOI can manage other environmental cleanups in their country. The DOS has funded the International Atomic Energy Agency (IAEA) to provide technical assistance to the GOI via a Technical Cooperation Project. Program coordination will be provided by the DOS, consistent with U.S. and GOI policies, and Sandia National Laboratories will be responsible for coordination of participants and for providing waste management support. Texas Tech University will continue to provide in-country assistance, including radioactive waste characterization and the stand-up of the Iraq Nuclear Services Company. The GOI owns the problems in Iraq and will be responsible for the vast majority of the implementation of the NDs Program. (authors)

Waste disposal

CERN Multimedia

2006-01-01

We should like to remind you that you can have all commonplace, conventional waste (combustible, inert, wood, etc.) disposed of by the TS-FM Group. Requests for the removal of such waste should be made by contacting FM Support on tel. 77777 or by e-mail (Fm.Support@cern.ch). For requests to be acted upon, the following information must be communicated to FM Support: budget code to be debited for the provision and removal of the skip / container. type of skip required (1m3, 4 m3, 7 m3, 15 m3, 20 m3, 30 m3). nature of the waste to be disposed of (bulky objects, cardboard boxes, etc.). building concerned. details of requestor (name, phone number, department, group, etc.). We should also like to inform you that the TS-FM Group can arrange for waste to be removed from work-sites for firms under contract to CERN, provided that the prior authorisation of the CERN Staff Member in charge of the contract is obtained and the relevant disposal/handling charges are paid. You are reminded that the selective sorting o...

Waste disposal

CERN Multimedia

2006-01-01

We should like to remind you that you can have all commonplace, conventional waste (combustible, inert, wood, etc.) disposed of by the TS-FM Group. Requests for the removal of such waste should be made by contacting FM Support on tel. 77777 or by e-mail (Fm.Support@cern.ch). For requests to be acted upon, the following information must be communicated to FM Support: budget code to be debited for the provision and removal of the skip / container; type of skip required (1m3, 4 m3, 7 m3, 15 m3, 20 m3, 30 m3); nature of the waste to be disposed of (bulky objects, cardboard boxes, etc.); building concerned; details of requestor (name, phone number, department, group, etc.). We should also like to inform you that the TS-FM Group can arrange for waste to be removed from work-sites for firms under contract to CERN, provided that the prior authorisation of the CERN Staff Member in charge of the contract is obtained and the relevant disposal/handling charges are paid. You are reminded that the selective sorting...

No nuclear power. No disposal facility?

Energy Technology Data Exchange (ETDEWEB)

Feinhals, J. [DMT GmbH und Co.KG, Hamburg (Germany)

2016-07-01

Countries with a nuclear power programme are making strong efforts to guarantee the safe disposal of radioactive waste. The solutions in those countries are large disposal facilities near surface or in deep geological layers depending on the activity and half-life of the nuclides in the waste. But what will happen with the radioactive waste in countries that do not have NPPs but have only low amounts of radioactive waste from medical, industrial and research facilities as well as from research reactors? Countries producing only low amounts of radioactive waste need convincing solutions for the safe and affordable disposal of their radioactive waste. As they do not have a fund by an operator of nuclear power plants, those countries need an appropriate and commensurate solution for the disposal of their waste. In a first overview five solutions seem to be appropriate: (i) the development of multinational disposal facilities by using the existing international knowhow; (ii) common disposal with hazardous waste; (iii) permanent storage; (iv) use of an existing mine or tunnel; (v) extension of the borehole disposal concept for all the categories of radioactive wastes.

Geological aspects of radioactive waste disposal

International Nuclear Information System (INIS)

Kobera, P.

1985-01-01

Geological formations suitable for burying various types of radioactive wastes are characterized applying criteria for the evaluation and selection of geological formations for building disposal sites for radioactive wastes issued in IAEA technical recommendations. They are surface disposal sites, disposal sites in medium depths and deep disposal sites. Attention is focused on geological formations usable for injecting self-hardening mixtures into cracks prepared by hydraulic decomposition and for injecting liquid radioactive wastes into permeable rocks. Briefly outlined are current trends of the disposal of radioactive wastes in Czechoslovakia and the possibilities are assessed from the geological point of view of building disposal sites for radioactive wastes on the sites of Czechoslovak nuclear power plants at Jaslovske Bohunice, Mochovce, Dukovany, Temelin, Holice (eastern Bohemia), Blahoutovice (northern Moravia) and Zehna (eastern Slovakia). It is stated that in order to design an optimal method of the burial of radioactive waste it will be necessary to improve knowledge of geological conditions in the potential disposal sites at the said nuclear plants. There is usually no detailed knowledge of geological and hydrological conditions at greater depths than 100 m. (Z.M.)

Comparison of the waste management aspects of spent fuel disposal and reprocessing: post-disposal radiological impact

International Nuclear Information System (INIS)

Mobbs, S.F.; Harvey, M.P.; Martin, J.S.; Mayall, A.; Jones, M.E.

1991-01-01

A joint project involving contractors from France, Germany and the UK was set up by the Commission of the European Communities to assess the implications of two waste management options: the direct disposal of spent fuel and reprocessing of that fuel. This report describes the calculation of the radiological impact on the public of the management and disposal of the wastes associated with these two options. Six waste streams were considered: discharge of liquid reprocessing effluents, discharge of gaseous reprocessing effluents, disposal of low-level solid wastes arising from reprocessing, disposal of intermediate-level solid wastes arising from reprocessing, disposal of vitrified high-level reprocessing wastes, and direct disposal of spent fuel. The results of the calculations are in the form of maximum annual doses and risks to individual members of the public, and collective doses to four population groups, integrated over six time periods. These results were designed for input into a computer model developed by another contractor, Yard Ltd, which combines costs and impacts in a multi-attribute hierarchy to give an overall measure of the impact of a given option

Design considerations for sealing the shafts of a nuclear fuel waste disposal vault

International Nuclear Information System (INIS)

Mortazavi, M.H.S.; Chan, H.T.; Radhakrishna, H.S.

1985-05-01

The shafts in an underground disposal system, which constitute potential pathways between the disposal vault and the biosphere, should be effectively sealed if the system is to perform as a hydrodynamic and geochemical barrier for the safe containment of nuclear fuel waste. In the design of the shaft backfill, consideration should be given to ensure that the backfill and the backfill/rock interface remain intact. Design-related problems, including critical pathways for the transport or radionuclides, configuration of shaft backfill and its functional requirements, the state of stress in a backfilled shaft with particular emphasis on the arching and load transfer phenomenon are discussed in this report

Optimal routes scheduling for municipal waste disposal garbage trucks using evolutionary algorithm and artificial immune system

Directory of Open Access Journals (Sweden)

Bogna MRÓWCZYŃSKA

2011-01-01

Full Text Available This paper describes an application of an evolutionary algorithm and an artificial immune systems to solve a problem of scheduling an optimal route for waste disposal garbage trucks in its daily operation. Problem of an optimisation is formulated and solved using both methods. The results are presented for an area in one of the Polish cities.

36 CFR 228.57 - Types of disposal.

Science.gov (United States)

2010-07-01

... 36 Parks, Forests, and Public Property 2 2010-07-01 2010-07-01 false Types of disposal. 228.57... Disposal of Mineral Materials Types and Methods of Disposal § 228.57 Types of disposal. Except as provided... qualified bidder after formal advertising and other appropriate public notice; (b) Sale by negotiated...

7 CFR 2902.21 - Disposable containers.

Science.gov (United States)

2010-01-01

... 7 Agriculture 15 2010-01-01 2010-01-01 false Disposable containers. 2902.21 Section 2902.21... Items § 2902.21 Disposable containers. (a) Definition. Products designed to be used for temporary... paragraph (d): Disposable containers can include boxes and packaging made from paper. Under the Resource...

Solid waste disposal into salt mines

International Nuclear Information System (INIS)

Repke, W.

1981-01-01

The subject is discussed as follows: general introduction to disposal of radioactive waste; handling of solid nuclear waste; technology of final disposal, with specific reference to salt domes; conditioning of radioactive waste; safety barriers for radioactive waste; practice of final disposal in other countries. (U.K.)

Compaction of solid wastes in countries without disposal facility: A prelude of future troubles

International Nuclear Information System (INIS)

Benitez-Navarro, J.C.; Salgado-Mojena, M.

2002-01-01

This paper is intended to launch a technical debate, which will lead up to simple recommendations on what to do with compactable solid wastes in countries without disposal facilities. The paper discusses the problems caused by some practical uncertainties in the long-term management of the radioactive solid wastes produced outside the nuclear fuel cycle, in countries belonging to Groups A, B and C. Compaction is the preferred volume reduction method. But the compacted solid wastes are very probably not in a suitable form for future disposal and would need to be processed again in the near future. (author)

Shallow ground disposal of radioactive wastes

International Nuclear Information System (INIS)

1981-01-01

This guidebook outlines the factors to be considered in site selection, design, operation, shut-down and surveillance as well as the regulatory requirements of repositories for safe disposal of radioactive waste in shallow ground. No attempt is made to summarize the existing voluminous literature on the many facets of radioactive waste disposal. In the context of this guidebook, shallow ground disposal refers to the emplacement of radioactive waste, with or without engineered barriers, above or below the ground surface, where the final protective covering is of the order of a few metres thick. Deep geological disposal and other underground disposal methods, management of mill tailings and disposal into the sea have been or will be considered in other IAEA publications. These guidelines have been made sufficiently general to cover a broad variety of climatic, hydrogeological and biological conditions. They may need to be interpreted or modified to reflect local conditions and national regulations

Classification and disposal of radioactive wastes

International Nuclear Information System (INIS)

Kocher, D.C.

1990-01-01

This paper reviews the historical development in the U.S. of definitions and requirements for permanent disposal of different classes of radioactive waste. We first consider the descriptions of different waste classes that were developed prior to definitions in laws and regulations. These descriptions usually were not based on requirements for permanent disposal but, rather, on the source of the waste and requirements for safe handling and storage. We then discuss existing laws and regulations for disposal of different waste classes. Current definitions of waste classes are largely qualitative, and thus somewhat ambiguous, and are based primarily on the source of the waste rather than the properties of its radioactive constituents. Furthermore, even though permanent disposal is clearly recognized as the ultimate goal of radioactive water management, current laws and regulations do not associated the definitions of different waste classes with requirement for particular disposal systems. Thus, requirements for waste disposal essentially are unaffected by ambiguities in the present waste classification system

Disposal of radioactive wastes

International Nuclear Information System (INIS)

Blomeke, J.O.

1979-01-01

Radioactive waste management and disposal requirements options available are discussed. The possibility of beneficial utilization of radioactive wastes is covered. Methods of interim storage of transuranium wastes are listed. Methods of shipment of low-level and high-level radioactive wastes are presented. Various methods of radioactive waste disposal are discussed

Progress towards the use of disposable filters

International Nuclear Information System (INIS)

Macphail, I.

1979-08-01

Thermally degradable materials have been evaluated for service in HEPA filter units used to filter gases from active plants. The motivation was to reduce the bulk storage problems of contaminated filters by thermal decomposition to gaseous products and a solid residue substantially comprised of the filtered particulates. It is shown that while there are no commercially available alternatives to the glass fibre used in the filter medium, it would be feasible to manufacture the filter case and spacers from materials which could be incinerated. Operating temperatures, costs and the type of residues for disposal are discussed for filter case materials. (U.K.)

Radioactive waste disposal in W.A

International Nuclear Information System (INIS)

Hartley, B.M.

1983-01-01

Radioactive waste in Western Australia arises primarily from medical diagnosis and treatment and from scientific research mainly with a medical orientation. Waste is classified before disposal depending on its level and type of radioactivity and then disposed of either to municipal land fill sites, to the sewerage system or by incineration. The amounts of radioactive materials which may be disposed of to the sewers and air are set by the Radiation Safety Act (1975) Regulations, and the land fill operations are controlled to ensure isolation of the material. Other waste such as unwanted sources used in industrial applications are stored for future disposal. Discussions are being held between officers of the State and Australian Governments aimed at providing suitable disposal methods for sources of this kind

On the pathway towards disposal. The need for long-term interim storage of high-level nuclear waste

International Nuclear Information System (INIS)

Budelmann, Harald; Koehnke, Dennis; Reichardt, Manuel

2017-01-01

The disposal of spent nuclear fuel is a still unsolved problem with social, ethical, economical, ecological and political dimensions. The stagnating decision process on the final repository concept in several countries has the consequence of the inclusion of long-term interim storage into the disposal concept. The contribution discusses several approaches. This opens the question whether the long-term interim storage is a matter of delaying tactic or a pragmatic solution on the way to a final repository.

36 CFR 13.1118 - Solid waste disposal.

Science.gov (United States)

2010-07-01

... 36 Parks, Forests, and Public Property 1 2010-07-01 2010-07-01 false Solid waste disposal. 13.1118... Provisions § 13.1118 Solid waste disposal. (a) A solid waste disposal site may accept non-National Park Service solid waste generated within the boundaries of the park area. (b) A solid waste disposal site may...

36 CFR 13.1008 - Solid waste disposal.

Science.gov (United States)

2010-07-01

... 36 Parks, Forests, and Public Property 1 2010-07-01 2010-07-01 false Solid waste disposal. 13.1008... § 13.1008 Solid waste disposal. (a) A solid waste disposal site may accept non-National Park Service solid waste generated within the boundaries of the park area. (b) A solid waste disposal site may be...

36 CFR 13.1912 - Solid waste disposal.

Science.gov (United States)

2010-07-01

... 36 Parks, Forests, and Public Property 1 2010-07-01 2010-07-01 false Solid waste disposal. 13.1912....1912 Solid waste disposal. (a) A solid waste disposal site may accept non-National Park Service solid waste generated within the boundaries of the park area. (b) A solid waste disposal site may be located...

36 CFR 13.1604 - Solid waste disposal.

Science.gov (United States)

2010-07-01

... 36 Parks, Forests, and Public Property 1 2010-07-01 2010-07-01 false Solid waste disposal. 13.1604... Solid waste disposal. (a) A solid waste disposal site may accept non-National Park Service solid waste generated within the boundaries of the park area. (b) A solid waste disposal site may be located within one...

Analysis of scenarios for the direct disposal of spent nuclear fuel disposal conditions as expected in Germany

International Nuclear Information System (INIS)

Ashton, P.; Mehling, O.; Mohn, R.; Wingender, H.J.

1990-01-01

This report contains an investigation of aspects of the waste management of spent light water reactor fuel by direct disposal in a deep geological formation on land. The areas covered are: interim dry storage of spent fuel with three options of pre-conditioning; conditioning of spent fuel for final disposal in a salt dome repository; disposal of spent fuel (heat-generating waste) in a salt dome repository; disposal of medium and low-level radioactive wastes in the Konrad mine. Dose commitments, effluent discharges and potential incidents were not found to vary significantly for the various conditioning options/salt dome repository types. Due to uncertainty in the cost estimates, in particular the disposal cost estimates, the variation between the three conditioning options examined is not considered as being significant. The specific total costs for the direct disposal strategy are estimated to lie in the range ECU 600 to 700 per kg hm (basis 1988)

Limitation of the EIA Process for the assessment of nuclear fuel waste disposal in Canada

Energy Technology Data Exchange (ETDEWEB)

Murphy, B.L.; Kuhn, R.G. [Guelph Univ., ON (Canada). Dept. of Geography

1999-12-01

The Canadian environmental impact assessment process for the Nuclear Fuel Waste Management and Disposal Concept was completed in 1994. Almost four years later, in February 1998, the Review Panel released its report. The viewpoints of those who participated in the assessment process is archived in the thousands of pages of hearing testimony, meeting transcripts and written briefs. One of the most contentious issues raised, and one that continues to plague management in Canada, is the debate surrounding how the problem of NFW waste management should be defined. The purpose of this paper is to critically assess the problem frame of the Canadian NFW management disposal concept EIS. This will be accomplished through an analysis of stakeholder participation and views, and through an evaluation of the range and nature of the information considered legitimate or constrained in the Canadian process.

Limitation of the EIA Process for the assessment of nuclear fuel waste disposal in Canada

International Nuclear Information System (INIS)

Murphy, B.L.; Kuhn, R.G.

1999-01-01

The Canadian environmental impact assessment process for the Nuclear Fuel Waste Management and Disposal Concept was completed in 1994. Almost four years later, in February 1998, the Review Panel released its report. The viewpoints of those who participated in the assessment process is archived in the thousands of pages of hearing testimony, meeting transcripts and written briefs. One of the most contentious issues raised, and one that continues to plague management in Canada, is the debate surrounding how the problem of NFW waste management should be defined. The purpose of this paper is to critically assess the problem frame of the Canadian NFW management disposal concept EIS. This will be accomplished through an analysis of stakeholder participation and views, and through an evaluation of the range and nature of the information considered legitimate or constrained in the Canadian process

Retrievable disposal - opposing views on ethics

International Nuclear Information System (INIS)

Selling, H.A.

2000-01-01

In the previous decades many research programmes on the disposal of radioactive waste have been completed in the Netherlands. The experts involved have reconfirmed their view that deep underground disposal in suitable geological formations would ensure a safe and prolonged isolation of the waste from the biosphere. Both rock salt and clay formations are considered to qualify as a suitable host rock. In 1993 the government in a position paper stated that such a repository should be designed in a way that the waste can be retrieved from it, should the need arise. In an attempt to involve stakeholders in the decision-making process, a research contract was awarded to an environmental group to study the ethical aspects related to retrievable disposal of radioactive waste. In their report which was published in its final form in January 2000 the authors concluded that retrievable disposal is acceptable from an ethical point of view. However, this conclusion was reached in the understanding that this situation of retrievability would be permanent. From the concept of equity between generations, each successive generation should be offered equal opportunities to decide for itself how to dispose of the radioactive waste. Consequently, the preferred disposal option is retrievable disposal (or long term storage) in a surface facility. Although this view is not in conformity with the ''official'' position on radioactive waste disposal, there is a benefit of having established a dialogue between interested parties in a broad sense. (author)

41 CFR 102-75.415 - What happens after the disposal agency receives the FAA's recommendation for disposal of the...

Science.gov (United States)

2010-07-01

... disposal agency receives the FAA's recommendation for disposal of the property for a public airport? 102-75... receives the FAA's recommendation for disposal of the property for a public airport? The head of the disposal agency, or his or her designee, may convey property approved by the FAA for use as a public...

Low-level radioactive wastes: Their treatment, handling, disposal

Energy Technology Data Exchange (ETDEWEB)

Straub, Conrad P [Robert A. Taft Sanitary Engineering Center, Radiological Health Research Activities, Cincinnati, OH(United States)

1964-07-01

The release of low level wastes may result in some radiation exposure to man and his surroundings. This book describes techniques of handling, treatment, and disposal of low-level wastes aimed at keeping radiation exposure to a practicable minimum. In this context, wastes are considered low level if they are released into the environment without subsequent control. This book is concerned with practices relating only to continuous operations and not to accidental releases of radioactive materials. It is written by use for those interested in low level waste disposal problems and particularly for the health physicist concerned with these problems in the field. It should be helpful also to water and sewage works personnel concerned with the efficiency of water and sewage treatment processes for the removal of radioactive materials; the personnel engaged in design, construction, licensing, and operation of treatment facilities; and to student of nuclear technology. After an introduction the following areas are discussed: sources, quantities and composition of radioactive wastes; collection, sampling and measurement; direct discharge to the water, soil and air environment; air cleaning; removal of radioactivity by water-treatment processes and biological processes; treatment on site by chemical precipitation , ion exchange and absorption, electrodialysis, solvent extraction and other methods; treatment on site including evaporation and storage; handling and treatment of solid wastes; public health implications. Appendices include a glossary; standards for protection against radiation; federal radiation council radiation protection guidance for federal agencies; site selection criteria for nuclear energy facilities.

The Hazardous Waste/Mixed Waste Disposal Facility

International Nuclear Information System (INIS)

Bailey, L.L.

1991-01-01

The Hazardous Waste/Mixed Waste Disposal Facility (HW/MWDF) will provide permanent Resource Conservation and Recovery Act (RCRA) permitted storage, treatment, and disposal for hazardous and mixed waste generated at the Department of Energy's (DOE) Savannah River Site (SRS) that cannot be disposed of in existing or planned SRS facilities. Final design is complete for Phase I of the project, the Disposal Vaults. The Vaults will provide RCRA permitted, above-grade disposal capacity for treated hazardous and mixed waste generated at the SRS. The RCRA Part B Permit application was submitted upon approval of the Permit application, the first Disposal Vault is scheduled to be operational in mid 1994. The technical baseline has been established for Phase II, the Treatment Building, and preliminary design work has been performed. The Treatment Building will provide RCRA permitted treatment processes to handle a variety of hazardous and mixed waste generated at SRS in preparation for disposal. The processes will treat wastes for disposal in accordance with the Environmental Protection Agency's (EPA's) Land Disposal Restrictions (LDR). A RCRA Part B Permit application has not yet been submitted to SCDHEC for this phase of the project. The Treatment Building is currently scheduled to be operational in late 1996

Safety considerations in the disposal of disused sealed radioactive sources in borehole facilities

CERN Document Server

International Atomic Energ Agency. Vienna

2003-01-01

Sealed radioactive sources are used in medicine, industry and research for a wide range of purposes. They can contain different radionuclides in greatly varying amounts. At the end of their useful lives, they are termed 'disused sources' but their activity levels can still be quite high. They are, for all practical purposes, another type of radioactive waste that needs to be disposed of safely. Disused sealed radioactive sources can represent a significant hazard to people if not managed properly. Many countries have no special facilities for the management or disposal of radioactive waste, as they have no nuclear power programmes requiring such facilities. Even in countries with developed nuclear programmes, disused sealed sources present problems as they often fall outside the common categories of radioactive waste for which disposal options have been identified. As a result, many disused sealed sources are kept in storage. Depending on the nature of the storage arrangements, this situation may represent a ...

ICRP recommendations and the safe disposal of radioactive waste

International Nuclear Information System (INIS)

Webb, G.A.M.; Barraclough, I.M.

1991-01-01

There are some special difficulties in setting up and applying radiological protection principle to the disposal of solid radioactive wastes. These were recognized by the International Commission on Radiological Protection (ICRP). One difficulty is the uncertain or probabilistic nature of some of the events or processes that could occur and affect the integrity of a waste repository. The other feature of solid waste disposal that causes difficulty is the length of time period of concern. The practical problem is the difficulties in predicting future conditions and in making the useful estimate of long term radiation impact with sufficient confidence. In this paper, the proposals made by the ICRP to deal with the above difficulties are briefly reviewed. Some suggestions are made as to how the criteria might be clarified, and the necessary calculation made to match the criteria. The reappraisal of the criteria for assessing the radiological safety of waste repositories is needed. (K.I.)

Separation, storage and disposal of krypton-85

International Nuclear Information System (INIS)

1980-01-01

Technical means available for the retention of 85 Kr and its immobilization, storage and disposal are reviewed. Cryogenic processes for the separation of krypton and xenon from diluting gases are discussed in more detail. Besides the cryogenic processes, a liquid adsorption process for reprocessing off-gases and charcoal adsorption and membrane processes for reactor off-gases are also dealt with. The retained krypton can be stored in pressurized containers with air or water cooling. The containers can be kept in engineered storage facilities for an intermediate period or until the 85 Kr has decayed. Alternatively, the krypton may be encapsulated in a solid. The injection of gases containing krypton into suitable geologic strata may also be possible. Much of the equipment required for the separation and storage of krypton, well known from ordinary technology, often needs some adaptation. Further R and D work is, however, needed to solve some problems which are specific to highly concentrated fission krypton. The subject is reviewed under the following headings: methods available for the separation of krypton from off-gases; separation of krypton from reactor off-gas; separation of krypton from reprocessing off-gas; conditioning methods; engineering storage; transportation; disposal

Spent nuclear fuel disposal liability insurance

International Nuclear Information System (INIS)

Martin, D.W.

1984-01-01

This thesis examines the social efficiency of nuclear power when the risks of accidental releases of spent fuel radionuclides from a spent fuel disposal facility are considered. The analysis consists of two major parts. First, a theoretical economic model of the use of nuclear power including the risks associated with releases of radionuclides from a disposal facility is developed. Second, the costs of nuclear power, including the risks associated with a radionuclide release, are empirically compared to the costs of fossil fuel-fired generation of electricity. Under the provisions of the Nuclear Waste Policy Act of 1982, the federally owned and operated spent nuclear fuel disposal facility is not required to maintain a reserve fund to cover damages from an accidental radionuclide release. Thus, the risks of a harmful radionuclide release are not included in the spent nuclear fuel disposal fee charged to the electric utilities. Since the electric utilities do not pay the full, social costs of spent fuel disposal, they use nuclear fuel in excess of the social optimum. An insurance mechanism is proposed to internalize the risks associated with spent fueled disposal. Under this proposal, the Federal government is required to insure the disposal facility against any liabilities arising from accidental releases of spent fuel radionuclides

Buried for ever: The US experience of radioactive waste disposal

International Nuclear Information System (INIS)

Resnikoff, M.