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Sample records for fixation waste treatment

  1. High level waste fixation in cermet form

    International Nuclear Information System (INIS)

    Kobisk, E.H.; Aaron, W.S.; Quinby, T.C.; Ramey, D.W.

    1981-01-01

    Commercial and defense high level waste fixation in cermet form is being studied by personnel of the Isotopes Research Materials Laboratory, Solid State Division (ORNL). As a corollary to earlier research and development in forming high density ceramic and cermet rods, disks, and other shapes using separated isotopes, similar chemical and physical processing methods have been applied to synthetic and real waste fixation. Generally, experimental products resulting from this approach have shown physical and chemical characteristics which are deemed suitable for long-term storage, shipping, corrosive environments, high temperature environments, high waste loading, decay heat dissipation, and radiation damage. Although leach tests are not conclusive, what little comparative data are available show cermet to withstand hydrothermal conditions in water and brine solutions. The Soxhlet leach test, using radioactive cesium as a tracer, showed that leaching of cermet was about X100 less than that of 78 to 68 glass. Using essentially uncooled, untreated waste, cermet fixation was found to accommodate up to 75% waste loading and yet, because of its high thermal conductivity, a monolith of 0.6 m diameter and 3.3 m-length would have only a maximum centerline temperature of 29 K above the ambient value

  2. Preliminary engineering and economic analysis of the fixation of high-level radioactive wastes in concrete

    International Nuclear Information System (INIS)

    Weeren, H.O.; Perona, J.J.

    1979-07-01

    This feasibility study was based on a waste fixation facility that would serve a reprocessing plant with a capacity of 5 metric tons of uranium per day (MTU/day). Postirradiation cooling times of 3 to 10 years prior to waste solidification were assumed. The waste solution would be concentrated, denitrated, mixed with cement, and cast under pressure in cylindrical canisters similar to those envisioned for a glass facility. The solidified waste grout would be vented, to allow the free water to escape, and then sealed. The filled canisters would be shipped to a geologic repository for permanent storage. Recent work with concretes formed under elevated temperatures and pressures (FUETAP) indicates that they are highly leach resistant. The operating costs were estimated for a waste fixation facility under several conditions. Operating costs for a glass fixation facility were also estimated and compared with the operating costs for a concrete fixation facility. The principal conclusion is that concrete could be an alternative to glass as a matrix for fixation of wastes with high heat-generation rates. The operating costs of an optimized concrete fixation process would probably not be greatly higher than the operating costs of a glass plant, and the capital costs would almost surely be lower. In addition, the concrete process is not a high-temperature process and would not have the consequent operating problems

  3. [Effectiveness comparison of suspension fixation plus hinged external fixator and double plate internal fixation in treatment of type C humeral intercondylar fractures].

    Science.gov (United States)

    Zhang, Jian; Lin, Xu; Zhong, Zeli; Wu, Chao; Tan, Lun

    2017-07-01

    To compare the effectiveness of suspension fixation plus hinged external fixator with double plate internal fixation in the treatment of type C humeral intercondylar fractures. Between January 2014 and April 2016, 30 patients with type C (Association for the Study of Internal Fixation, AO/ASIF) humeral intercondylar fractures were treated. Kirschner wire suspension fixation plus hinged external fixator was used in 14 cases (group A), and double plate internal fixation in 16 cases (group B). There was no significant difference in gender, age, injury cause, disease duration, injury side, and type of fracture between 2 groups ( P >0.05). There was no significant difference in operation time and hospitalization stay between 2 groups ( P >0.05). But the intraoperative blood loss in group A was significantly less than that in group B ( P internal fixation removal, the intraoperative blood loss, and VAS score at 1 day and 3 days after operation in group A were significant better than those in group B ( P external fixator and double plate internal fixation for the treatment of type C humeral intercondylar fractures have ideal outcome in elbow function. But the suspension fixation plus hinged external fixator is better than double plate internal fixation in intraoperative blood loss, postoperative VAS score, and time of internal fixation removal.

  4. Markisa fruit (Passiflora edulis var. flavicarpa) as a fixation material of natural colour of mangrove waste on batik

    Science.gov (United States)

    Izzah, S. N.; Marwoto, P.; Iswari, R. S.

    2018-03-01

    The process of natural colouring of batik using mangrove waste with the markisa fruit as a fixation material has been reported. In this experiment, the fixation material of markisa fruit has been compared with the commonly used fixation materials, such as CaCO3, AlK(SO4)2, and FeSO4 as material controls. Both grey scale and staining scale have been used as standard evaluations. Based on the Indonesian National Standard (SNI) it can be shown that batik with markisa fruit as a fixation material has a colour fastness value against average washing at good-excellent level (4-5) and colour fastness value to sunshine is moderate-excellent level (3-5). Thus, we conclude that Markisa fruit can be used as a fixation material in the colouring process of natural colour batik from mangrove waste.

  5. Development of cermets for high-level radioactive waste fixation

    International Nuclear Information System (INIS)

    Aaron, W.S.; Quinby, T.C.; Kobisk, E.H.

    1979-01-01

    A method is currently under development for the solidification and fixation of commercial and defense high-level radioactive wastes in the form of ceramic particles encapsulated by metal, i.e., a cermet. The chemical and physical processing techniques which have been developed and the properties of the resulting cermet bodies are described in this paper. These cermets have the advantages of high thermal conductivity and low leach rates

  6. Effectiveness of external fixator combined with T-plate internal fixation for the treatment of comminuted distal radius fractures.

    Science.gov (United States)

    Han, L R; Jin, C X; Yan, J; Han, S Z; He, X B; Yang, X F

    2015-03-31

    This study compared the efficacy between external fixator combined with palmar T-plate internal fixation and simple plate internal fixation for the treatment of comminuted distal radius fractures. A total of 61 patients classified as type C according to the AO/ASIF classification underwent surgery for comminuted distal radius fractures. There were 54 and 7 cases of closed and open fractures, respectively. Moreover, 19 patients received an external fixator combined with T-plate internal fixation, and 42 received simple plate internal fixation. All patients were treated successfully during 12-month postoperative follow-up. The follow-up results show that the palmar flexion and dorsiflexion of the wrist, radial height, and palmar angle were significantly better in those treated with the external fixator combined with T-plate compared to those treated with the simple plate only (P 0.05). Hence, the effectiveness of external fixator combined with T-plate internal fixation for the treatment of comminuted distal radius fractures was satisfactory. Patients sufficiently recovered wrist, forearm, and hand function. In conclusion, compared to the simple T-plate, the external fixator combined with T-plate internal fixation can reduce the possibility of the postoperative re-shifting of broken bones and keep the distraction of fractures to maintain radial height and prevent radial shortening.

  7. Status report: waste incineration and fixation for Waste Management, Production, and Reprocessing Division of the Department of Energy (July--December 1976)

    International Nuclear Information System (INIS)

    Ziegler, D.L.; White, J.W.; Johnson, A.J.; Fong, L.Q.; Teter, A.R.; Chung, S.F.

    1977-01-01

    Fluidized bed incineration and waste fixation processes are being used to process the types of wastes expected from nuclear fuel reprocessing and production plants. Test incineration runs have been made on two types of wastes: high efficiency particulate air (HEPA) filters and tributyl phosphate-solvent solutions. Laboratory-scale vitrification equipment was used to produce glass pellets from incinerator ash and blends of other expected waste streams. Computer modeling gave an expected product integrity life of over 2,000 years

  8. Quarterly Progress Report Research And Development Activities Waste Fixation Program October Through December 1976

    International Nuclear Information System (INIS)

    McElroy, J. L.

    1977-01-01

    Research and development activities of the Waste Fixation Program for October through December 1976 are described in this report. The objective of this program is to develop processes to convert high-level radioactive liquid waste (HLLW) to solid forms that are demonstrated to be physically, chemically, and radiolytically stable and inert. The scope of this program encompasses plans to make available a flexible advancing technology for the solidification of radioactive waste. Early technology will produce borosilicate glass by in-can melting and continuous electric melters. Multibarrier waste forms will be developed for future application

  9. Surgical treatment of neglected clubfoot using external fixator

    Directory of Open Access Journals (Sweden)

    Rodrigo Mota Pacheco Fernandes

    Full Text Available ABSTRACT The definition of neglected clubfoot (NC includes a variable range of complex deformities of the foot that are refractory to conventional treatments or are treated inappropriately. Several etiologies may be related to this. The Ilizarov method has become established as a tool for treating these deformities. It minimizes soft-tissue damage through gradual correction of the deformity, with a high success rate in relation to achieving a plantigrade foot, with low incidence of recurrence. The indications for treatment include severe rigid deformities (Dimeglio III and IV, or adverse skin conditions. Careful clinical and radiological examination is fundamental for proper planning and installation of the external fixator. The techniques used include selection of external fixation assemblies, which can be closed when there is a connection between the leg, hindfoot and forefoot. This closed assembly may or may not be constricted, according to whether hinges are provided or whether use of the natural anatomical hinges during correction of the deformity is envisaged. An open assembly makes it possible to add flexibility to the foot through histogenesis, while allowing closed corrections of greater precision later on. Hexapod fixators are an innovation with high potential for accuracy in correcting deformities. Procedures associated with external fixation include soft-tissue release and bone procedures. These procedures enable corrections that are more anatomical, for different degrees of severity and stiffness of deformity. It can be concluded from analyzing this case series that treatment of neglected clubfoot using an external fixator has a high rate of good and excellent results, with low frequency of complications.

  10. Use of fixation techniques in processing radioactive wastes from nuclear power plants in Czechoslovakia

    International Nuclear Information System (INIS)

    Seliga, M.

    1977-01-01

    The current state of radioactive waste disposal from the Bohunice nuclear power plant is described. The method of vacuum cementation was chosen for solidifying liquid radioactive wastes. This method makes it possible to obtain a product whose properties, namely strength, leachability, and radiation stability allow for the production of blocks without packing material. Also solved was the fixation of liquid radioactive waste using bituminization based on mixing liquid radioactive waste with aqueous bitumen emulsion in a film evaporator in which the mixture of liquid radioactive wastes and bitumen emulsion evaporate producing solid bitumen. The parameters are given of the cementation and bituminization lines which are designed for use in nuclear power plants with WWER type reactors. (J.B.)

  11. [Case-control study on T-shaped locking internal fixation and external fixation for the treatment of dorsal Barton's fracture].

    Science.gov (United States)

    Chen, Huan-qing; Wen, Xi-le; Li, Yang-ming; Wen, Cong-you

    2015-06-01

    To compare clinical effect of T-shaped locking internal fixation and external fixation in treating dorsal Barton's fracture,and investigate selective strategy of internal fixation. From January 2008 to January 2013, 100 patients with dorsal Barton's fracture were randomly divided into two groups. In treatment group, there were 30 males and 20 females with an average age of (33.8±3.6) years old;30 cases were type B, 20 cases were type C;and treated with T-shaped locking internal fixation. In control group, there were 32 male and 18 females with an average age of (32.9±3.4) years old; 29 cases were type B, 21 cases were type C; and treated with external fixation. Volar tilt, ulnar deviation and radial height at 3 months after operation were detected and compared between two groups. Mechara functional evaluation were used to evaluate postoperative clinical effects. Clinical cure time, postoperative complications,joint mobility and function score were recorded and compared between two groups. In treatment group,volar tilt was (11.9±2.7)°, ulnar deviation was (20.8+ 2.9)°,and radial height was (10.9±1.8) mm; while volar tilt was (9.1±1.6)°, ulnar deviation was (17.1±2.9)°, and radial height was (8.1±1.5) mm in control group. Treatment group was better than control group in volar tilt, ulnar deviation and radial height. Clinical cure time in treatment group was(12.0±2.3) weeks, shorter than control group (18.0±4.1) weeks. The incidence of complications in treatment group was lower than control group. According to Mehara functional evaluation,20 cases got excellent results, 25 good, 3 moderate and 2 poor in treatment group; 16 cases got excellent results, 14 good, 10 moderate and 10 poor in control group. Treatment group was better than control group in clinical effects. T-shaped locking internal fixation with postoperative functional exercise for the treatment of dorsal Barton's fracture fits for biomechanics demands,and has advantages of stable fixation

  12. [Treatment of pediatric distal femur fractures by external fixator combined with limited internal fixation].

    Science.gov (United States)

    Wei, Sheng-wang; Shi, Zhan-ying; Hu, Ju-zheng; Wu, Hao

    2016-03-01

    To discuss the clinical effects of external fixator combined with limited internal fixation in the treatment of pediatric distal femur fractures. From January 2008 to June 2014, 17 children of distal femur fractures were treated by external fixator combined with limited internal fixation. There were 12 males and 5 females, aged from 6 to 13 years old with an average of 10.2 years, ranged in the course of disease from 1 h to 2 d. Preoperative diagnoses were confirmed by X-ray films in all children. There were 11 patients with supracondylar fracture , and 6 patients with intercondylar comminuted fracture. According to AO/ASIF classification, 9 fractures were type A1, 5 cases were type A2,and 3 cases were type C1. The intraoperative and postoperative complications, postoperative radiological examination, lower limbs length and motion of knee joints were observed. Knee joint function was assessed by KSS score. All the patients were followed up from 6 to 38 months with an average of 24.4 months. No nerve or blood vessel injury was found. One case complicated with the external fixation loosening, 2 cases with the infection of pin hole and 3 cases with the leg length discrepancy. Knee joint mobility and length measurement (compared with the contralateral), the average limited inflexion was 10 degrees (0 degrees to 20 degrees), the average limited straight was 4 degrees (0 degrees to 10), the average varus or valgus angle was 3 degrees (0 degrees to 5 degrees). KSS of the injured side was (96.4 +/- 5.0) points at final follow-up, 16 cases got excellent results and 1 good. All fractures obtained healing and no epiphyseal closed early was found. External fixator combined with limited internal fixation has advantages of simple operation, reliable fixation, early functional exercise in treating pediatric distal femurs fractures.

  13. Fixation of calcined waste by bituminization or cementation

    International Nuclear Information System (INIS)

    Napravnik, J.; Kyrs, M.; Ditl, P.

    1983-01-01

    The overall concept is given of the combination of calcination with fixation into bitumen, cement etc. The design is shown of a calciner with the capacity of 10 L/h which was tested on real radioactive wastes for 2000 h. The geometrical and operating parameters of the apparatus have been optimized based on a statistical evaluation of the experiments. Wastes containing nitrates are calcined at 300-550 deg. C, yielding oxides. Wastes containing sulphates, carbonates, KMnO 4 , or borates are calcined at 150-330 deg. C, yielding soluble salts. The content of H 3 BO 4 and Na 2 B 4 O 7 and in some cases of sulphates in the calcinate retards hardening of the mixture with cement. Nitrates and detergents also interfere. The effect of the above components on the products mixed with bitumen is much less. Detergents can be decomposed at 200-300 deg. C; organic acids can be reacted with A1 salts to form insoluble substances lowering the leaching rate of Sr and Cs; small amounts of SiO 2 eliminate the effect of borates on cement hardening. The drawbacks of bituminization with bitumen emulsions are the complicated preparation of the emulsion, higher leaching rate of the product and low stability of the emulsion against breaking. The leachability was determined (1-50 days) of different products containing LWR wastes: 33% of concentrated waste in cement of calcination product stabilized with PVA exhibit approx. 8x10 - 3 g/cm 2 per day, 33% of calcine in cement approx. 3x10 - 3 ; 40% concentrate fixed with bitumen emulsion approx. 9x10 - 4 ; 50% calcine stabilized with PVA in bitumen, pilot-plant scale approx. 2x10 - 5 ; the same but on a laboratory scale approx. 1.10 - 5 . (author)

  14. [Treatment of femoral neck fracture--preference to internal fixation].

    Science.gov (United States)

    Minato, Izumi

    2011-03-01

    In the guidelines for the treatment of femoral neck fracture, prosthetic replacement is recommended in displaced one and internal fixation is in undisplaced one. However, in the long view, survived femoral head after internal fixation can be superior to prosthesis which will deteriorate as time goes by. Surgical method should be considered not only by type of fracture but general status of the patient.

  15. Quality control of radioactive waste products

    International Nuclear Information System (INIS)

    Martens, B.R.; Warnecke, E.; Odoj, R.

    1986-01-01

    The variety of incoming untreated wastes, treatment methods, waste forms and containers requires a great variety of controlling methods and principles to be applied both during waste treatment and on the final product. The paper describes product control schemes and methods, sampling systems and transportable testing equipment for waste drums, and equipment for waste cementation using in-drum stirring and subsequent fixation of solid wastes in the flowable product. (DG) [de

  16. Treatment of complex osteoarticular injuries of the elbow with external unilateral articulated fixator

    International Nuclear Information System (INIS)

    Cuellar Gallo, Lazaro; Portilla Carrillo, Armando; Calderon Uribe, Oscar; Calvache Currea, Gustavo Adolfo; Satizabal Azuero, Carlos Arnulfo

    2001-01-01

    Previous observations suggest that conventional treatment of complex injuries about the elbow such as open; reduction and internal Fixation might lead, to bad functional outcome. The authors present a descriptive, observational and prospective study of a series of cases, on 8 patients, average age 37.8 years (25-28 years) 6 men and 2 women with complex injury of the elbow. Due to trauma which etiology is summarized as follows intraarticular comminuted open fracture secondary to gunshot wound 5 patients (62.5%); luxofracture 2 patients (25%), lntraarticular comminuted closed fracture 1 patient (12.5%). The patients where followed for 8 to 20 months. Were performed en 75% of patients open reduction, internal fixation of radial resection of radial head en 25% when comminute fracture of the head was found. All patients were treated with an external unilateral articulated fixation on the elbow, in order to protect the internal fixation, allow early joint motion and give early mobility. All patients were evaluated with Mayo scale, obtaining good results, with externals fixation treatment. In one case (12.5%) a dyaphiseal fracture of the humerus, occurred as an inherent complication secondary to the use of the external fixation, after it's withdrawal. This patient was treated with open reduction and internal fixation of the fracture, without significant impairment of the final result. Early results suggest that the use of unilateral articulated external fixator for the treatment of complex fractures about the elbow has great advantages over the other treatment techniques, such as the early motion of the elbow, dynamic protection of the internal fixation and preservation of the articulate stability, even when ligament injury is present

  17. High-level radioactive waste fixation in sintered vitreous matrix

    International Nuclear Information System (INIS)

    Russo, D.O.; Messi de Bernasconi, N.; Audero, M.A.

    1987-01-01

    The safe storage of high-level wastes from fuel elements reprocessing includes, as a first step, the fixation of the same in materials having a good resistance to the leaching in aqueous medium, such as borosilicate glass. As an alternative to the usual method of the molten glasses, a procedure for the sintering of a powdered glass and waste mixture at lower temperatures (600-700 deg C) has been developed, which minimizes the volatilization of active compounds during the process. Two glasses matrices of different composition and characteristics were used, to which the simulated wastes were added in the ratio of a 10% in weight of oxides. Two sintering techniques were employed 1: cold pressing and further sintering; 2: hot pressing and sintering under pressure. The densities were measured, the microstructure of the samples was analyzed and leaching essays were made in distilled water. The pellet's microstructure was observed by means of optical microscopy, by reflection in polished samples and by transparency in thin slices. The presence of crystalline compounds was analyzed by means of x rays and electron microprobe. The results have shown the convenience to continue with hot pressing essays, because a denser product with a higher resistance to the leaching is thus obtained. (M.E.L.) [es

  18. Use of glass-ceramic materials for the fixation of radioactive wastes

    International Nuclear Information System (INIS)

    Minaev, A.A.; Oziraner, S.N.; Prokhorova, N.P.

    1979-01-01

    This paper is concerned with the study of the crystallization of phosphate and silicate glasses. It was shown that temperature and time of storage influence considerably the crystallization of glasses and that crystallization very often increases their rates of leaching to a great extent. However, there are glasses in which crystallization does not result in leaching rate increase. It seems reasonable to use these materials for the fixation of radioactive wastes. The main reasons for the increase in the leaching rate during crystallization are the formation of porosity and soluble crystal phases

  19. [Staple fixation for the treatment of hamate metacarpal joint injury].

    Science.gov (United States)

    Tang, Yang-Hua; Zeng, Lin-Ru; Huang, Zhong-Ming; Yue, Zhen-Shuang; Xin, Da-Wei; Xu, Can-Da

    2014-03-01

    To investigate the effcacy of the staple fixation for the treatment of hamate metacarpal joint injury. From May 2009 to November 2012,16 patients with hamate metacarpal joint injury were treated with staple fixation including 10 males and 6 females with an average age of 33.6 years old ranging from 21 to 57 years. Among them, 11 cases were on the fourth or fifth metacarpal base dislocation without fractures, 5 cases were the fourth or fifth metacarpal base dislocation with avulsion fractures of the back of hamatum. Regular X-ray review was used to observe the fracture healing, joint replacement and position of staple fixation. The function of carpometacarpal joint and metacarpophalangeal joint were evaluated according to ASIA (TAM) system evaluation method. All incision were healed well with no infection. All patients were followed up from 16 to 24 months with an average of (10.0 +/- 2.7) months. No dislocation recurred, the position of internal fixator was good,no broken nail and screw withdrawal were occurred. Five patients with avulsion fracture of the back of hamatum achieved bone healing. The function of carpometacarpal joint and metacarpophalangeal was excellent in 10 cases,good in 5 cases, moderate in 1 case. The application of the staple for the treatment of hamatometacarpal joint injury has the advantages of simple operation, small trauma, reliable fixation, early postoperative function exercise and other advantages, which is the ideal operation mode for hamatometacarpal joint injury.

  20. [Case-control study on effects of external fixation combined with limited internal fixation for the treatment of Pilon fractures of Rüedi-Allgower type III].

    Science.gov (United States)

    Duan, Da-Peng; You, Wu-Lin; Ji, Le; Zhang, Yong-Tao; Dang, Xiao-Qian; Wang, Kun-Zheng

    2014-01-01

    To analyze the effects of three surgical operations in the treatment of Pilon fracture of Rüedi-Allgower type III, and put forward the best therapeutic method. The clinical data of 33 patients with Pilon fracture who received surgical operations (plaster immobilization group, 10 cases; distal tibia anatomical plate group, 11 cases; external fixation with limited internal fixation group, 12 cases) from October 2009 to January 2012 were analyzed. There were 5 males and 5 females, ranging in age from 24 to 61 years in the plaster immobilization group. There were 7 males and 4 females, ranging in age from 21 to 64 years in the distal tibia anatomical plate group. There were 7 males and 5 females, ranging in age from 23 to 67 years in the external fixation with limited internal fixation group. The Ankle X-ray of Pilon fracture after operation, ankle score, early and late complications were collected. Bourne system was used to evaluate ankle joint function. After 8 months to 3 years follow-up, it was found that three kinds of treatment had significant differences in the outcomes and complications (P external fixation with limited internal fixation group got the best results. The number of anatomic reduction cases in the external fixation with limited internal fixation group (7 cases) and the distal tibia anatomical plate group (8 cases) was more than the plaster immobilization group (2 cases). According to the ankle score, 8 patients got an excellent result, 3 good and 1 poor in the limited internal fixation group ,which was better than those of distal tibia anatomical plate group (5 excellent, 4 good and 2 poor) and the plaster immobilization group (3 excellent, 4 good and 3 poor). The number of early and late complications in the external fixation with limited internal fixation group was more than those in the plaster immobilization group and the distal tibia anatomical plate group (Pexternal fixation with limited internal fixation in the treatment of Pilon fracture

  1. [Effectiveness comparison of flexible fixation and rigid fixation in treatment of ankle pronation-external rotation fractures with distal tibiofibular syndesmosis].

    Science.gov (United States)

    Li, Yuewei; Zhang, Minghui; Li, Xiaorong; Chen, Xiaoyong; Deng, Jianlong

    2017-07-01

    To compare the effectiveness of flexible fixation and rigid fixation in the treatment of ankle pronation-external rotation fractures with distal tibiofibular syndesmosis. A retrospective analysis was made on the clinical data of 50 patients with ankle pronation-external rotation fractures and distal tibiofibular syndesmosis treated between January 2013 and December 2015. Suture-button fixation was used in 23 patients (flexible fixation group) and cortical screw fixation in 27 patients (rigid fixation group). There was no significant difference in age, gender, weight, side, fracture type, and time from trauma to surgery between 2 groups ( P >0.05). The operation time, medial clear space (MCS), tibiofibular clear space (TFCS), tibiofibular overlap (TFO), American Orthopaedic Foot and Ankle Society (AOFAS) score, and Foot and Ankle Disability Index (FADI) score were compared between 2 groups. The operation time was (83.0±9.1) minutes in the flexible fixation group and was (79.6±13.1) minutes in the rigid fixation group, showing no significant difference ( t =1.052, P =0.265). All patients achieved healing of incision by first intention. The patients were followed up 12-20 months (mean, 14 months). The X-ray films showed good healing of fracture in 2 groups. There was no screw fracture, delayed union or nounion. The fracture healing time was (12.1±2.5) months in the flexible fixation group and was (11.3±3.2) months in the rigid fixation group, showing no significant difference between 2 groups ( t =1.024, P =0.192). Reduction loss occurred after removal of screw in 2 cases of the rigid fixation group. At last follow-up, there was no significant difference in MCS, TFCS, TFO, AOFAS score and FADI score between 2 groups ( P >0.05). Suture-button fixation has similar effectiveness to screw fixation in ankle function and imaging findings, and flexible fixation has lower risk of reduction loss of distal tibiofibular syndesmosis than rigid fixation.

  2. Treatment of Bottled Liquid Waste During Remediation of the Hanford 618-10 Burial Ground - 13001

    International Nuclear Information System (INIS)

    Faulk, Darrin E.; Pearson, Chris M.; Vedder, Barry L.; Martin, David W.

    2013-01-01

    A problematic waste form encountered during remediation of the Hanford Site 618-10 burial ground consists of bottled aqueous waste potentially contaminated with regulated metals. The liquid waste requires stabilization prior to landfill disposal. Prior remediation activities at other Hanford burial grounds resulted in a standard process for sampling and analyzing liquid waste using manual methods. Due to the highly dispersible characteristics of alpha contamination, and the potential for shock sensitive chemicals, a different method for bottle processing was needed for the 618-10 burial ground. Discussions with the United States Department of Energy (DOE) and United States Environmental Protection Agency (EPA) led to development of a modified approach. The modified approach involves treatment of liquid waste in bottles, up to one gallon per bottle, in a tray or box within the excavation of the remediation site. Bottles are placed in the box, covered with soil and fixative, crushed, and mixed with a Portland cement grout. The potential hazards of the liquid waste preclude sampling prior to treatment. Post treatment verification sampling is performed to demonstrate compliance with land disposal restrictions and disposal facility acceptance criteria. (authors)

  3. Treatment of Bottled Liquid Waste During Remediation of the Hanford 618-10 Burial Ground - 13001

    Energy Technology Data Exchange (ETDEWEB)

    Faulk, Darrin E.; Pearson, Chris M.; Vedder, Barry L.; Martin, David W. [Washington Closure Hanford, LLC, Richland, WA 99354 (United States)

    2013-07-01

    A problematic waste form encountered during remediation of the Hanford Site 618-10 burial ground consists of bottled aqueous waste potentially contaminated with regulated metals. The liquid waste requires stabilization prior to landfill disposal. Prior remediation activities at other Hanford burial grounds resulted in a standard process for sampling and analyzing liquid waste using manual methods. Due to the highly dispersible characteristics of alpha contamination, and the potential for shock sensitive chemicals, a different method for bottle processing was needed for the 618-10 burial ground. Discussions with the United States Department of Energy (DOE) and United States Environmental Protection Agency (EPA) led to development of a modified approach. The modified approach involves treatment of liquid waste in bottles, up to one gallon per bottle, in a tray or box within the excavation of the remediation site. Bottles are placed in the box, covered with soil and fixative, crushed, and mixed with a Portland cement grout. The potential hazards of the liquid waste preclude sampling prior to treatment. Post treatment verification sampling is performed to demonstrate compliance with land disposal restrictions and disposal facility acceptance criteria. (authors)

  4. VUJE experience with cementation of liquid and wet radioactive waste

    International Nuclear Information System (INIS)

    Kravarik, Kamil; Holicka, Zuzana; Pekar, Anton; Zatkulak, Milan

    2011-01-01

    Liquid and wet LLW generated during operation as well as decommissioning of NPPs is treated with different methods and fixed in a suitable fixation matrix so that a final product meets required criteria for its disposal in a final repository. Cementation is an important process used for fixation of liquid and wet radioactive waste such as concentrate, spent resins and sludge. Active cement grout is also used for fixation of low level solid radioactive waste loaded in final packing containers. VUJE Inc. has been engaged in research of cementation for long. The laboratory for analyzing radioactive waste properties, prescription of cementation formulation and estimation of final cement product properties has been established. Experimental, semi-production cementation plant has been built to optimize operation parameters of cementation. VUJE experience with cementation of liquid and wet LLW is described in the presented paper. VUJE has assisted in commissioning of Jaslovske Bohunice Treatment Centre. Cement formulations for treatment of concentrate, spent resins and sludge have been developed. Research studies on the stability of a final concrete packaging container for disposal in repository have been performed. Gained experience has been further utilized for design and manufacture of several cementation plants for treatment of various liquid and wet LLW. Their main technological and technical parameters as well as characterization of treated waste are described in the paper. Applications include the Mochovce Final Treatment Centre, Movable Cementation Facility utilizing in-drum mixing for treatment of sludge, Cementation Facility for treatment of tritiated water in Latvia and Cementation Facility for fixation of liquid and solid institutional radioactive waste in Bulgaria, which utilizes lost stirrer mixer. (author)

  5. Radioactive waste processing

    International Nuclear Information System (INIS)

    Dejonghe, P.

    1978-01-01

    This article gives an outline of the present situation, from a Belgian standpoint, in the field of the radioactive wastes processing. It estimates the annual quantity of various radioactive waste produced per 1000 MW(e) PWR installed from the ore mining till reprocessing of irradiated fuels. The methods of treatment concentration, fixation, final storable forms for liquid and solid waste of low activity and for high level activity waste. The storage of radioactive waste and the plutonium-bearing waste treatement are also considered. The estimated quantity of wastes produced for 5450 MW(e) in Belgium and their destination are presented. (A.F.)

  6. Skin Graft Fixation Using Hydrofiber (Aquacel® Extra).

    Science.gov (United States)

    Yen, Ya-Hui; Lin, Chih-Ming; Hsu, Honda; Chen, Ying-Chen; Chen, Yi-Wen; Li, Wan-Yu; Hsieh, Chia-Nan; Huang, Chieh-Chi

    2018-06-01

    The traditional method of skin graft fixation is with tie-over bollus dressing. The use of splints in the extremities for skin graft fixation is a common practice. However, these splints are heavy and uncomfortable and contribute considerably to our overall medical waste. Hydrofiber (Aquacel Extra) has a strong fluid absorption property and fixates well to the underlying wound once applied. In this study, we used hydrofiber for fixation, avoiding the use of splints after skin grafting. A total of 56 patients reconstructed with split-thickness skin graft that was fixated only with hydrofiber between March 2015 and March 2016 were included in this retrospective study. There were 44 men and 12 women with a mean age of 61 ± 18 years. The defect size ranged from 1 × 1 cm for fingertips to 30 × 12 cm for lower limb defects. The average defect size was 61 ± 78 cm. The mean skin graft take was 96% ± 6%. Because splints were not required, we saved around 48 kg of medical waste over the space of 1 year. The use of hydrofiber for skin graft fixation was effective and technically very simple. Splints were not required with this method, decreasing the medical waste created and increasing patient comfort. We suggest that this is an excellent alternative for skin graft fixation while at the same time decreasing our carbon footprint as surgeons.

  7. Pedicle screw-rod fixation: a feasible treatment for dogs with severe degenerative lumbosacral stenosis.

    Science.gov (United States)

    Tellegen, Anna R; Willems, Nicole; Tryfonidou, Marianna A; Meij, Björn P

    2015-12-07

    Degenerative lumbosacral stenosis is a common problem in large breed dogs. For severe degenerative lumbosacral stenosis, conservative treatment is often not effective and surgical intervention remains as the last treatment option. The objective of this retrospective study was to assess the middle to long term outcome of treatment of severe degenerative lumbosacral stenosis with pedicle screw-rod fixation with or without evidence of radiological discospondylitis. Twelve client-owned dogs with severe degenerative lumbosacral stenosis underwent pedicle screw-rod fixation of the lumbosacral junction. During long term follow-up, dogs were monitored by clinical evaluation, diagnostic imaging, force plate analysis, and by using questionnaires to owners. Clinical evaluation, force plate data, and responses to questionnaires completed by the owners showed resolution (n = 8) or improvement (n = 4) of clinical signs after pedicle screw-rod fixation in 12 dogs. There were no implant failures, however, no interbody vertebral bone fusion of the lumbosacral junction was observed in the follow-up period. Four dogs developed mild recurrent low back pain that could easily be controlled by pain medication and an altered exercise regime. Pedicle screw-rod fixation offers a surgical treatment option for large breed dogs with severe degenerative lumbosacral stenosis with or without evidence of radiological discospondylitis in which no other treatment is available. Pedicle screw-rod fixation alone does not result in interbody vertebral bone fusion between L7 and S1.

  8. Posterior treatment of delayed traumatic atlantoaxial joint dislocation with apofix internal fixation

    International Nuclear Information System (INIS)

    Qing Wei; Jiang Weimin; Shi Jinhui; Li Xuefeng; Yang Huilin; Tang Tiansi

    2010-01-01

    Objective: To assess the effect of posterior fixation and fusion with Apofix device for the treatment of delayed traumatic atlantoaxial joint dislocation. Methods: Eighteen patients with delayed traumatic atlantoaxial joint dislocation were included. Posterior fixation and fusion with Apofix device were performed. First step was one or two week skull traction. After the atlantoaxial joint dislocation had been reduced, the posterior fixation and fusion with Apofix was performed. Using local anaesthesia, atlantoaxial interval and posterior structure of atlas and dentata were exposed by midline operative approach. Apofix interlaminar clamps were placed at posterior arch of atlas and odontoid vertebral laminae, autologous iliac bone graft was placed for fusion. Then the device to proper position was pressurized and items locked. Results: All of the patients were followed up, the mean follow-up period was 38 months (13 ∼ 84 months). Fifteen patients obtained complete reduction, the others were partial reduction. Seventeen patients had successful fusion after 3 or 4 months, only 1 patient who had partial reduction had internal fixation loose and nonfusion, leading to recurrence of atlantoaxial joint dislocation. An occipitocervical fusion surgery was performed on this patient. As to neurological assessment, 16 patients had neurological deficit before operation, while 6 of them recovered completely after operation, another 10 patients' neurological status improved significantly. JOA score was improved from 9.5 pre-operative to 15.8 post-operative. Conclusion: Apofix internal fixation and fusion seems to be feasible in treatment of delayed traumatic atlantoaxial joint dislocation. Successful reduction before operation and proper treatment after operation is also important. (authors)

  9. Report About the Design of External Fixator for Treatment of Pelvis and Acetabulum Fractures

    Directory of Open Access Journals (Sweden)

    Martin JANEČKA

    2012-06-01

    Full Text Available Main point in this contribution is the design of external fixators applied in traumatology and orthopaedics. These fixators can be used in the treatment of open and unstable (i.e. complicated fractures of pelvis and its acetabulum. Numerical modelling (i.e. Finite Element Method, together with CAD modelling, experiments, material engineering, and nanotechnology are presented as a support for developing of a new design of external fixators.

  10. Surgical treatment of children with non-traumatic old atlanto-axial rotatory fixation

    Directory of Open Access Journals (Sweden)

    A. V. Gubin

    2015-01-01

    Full Text Available Atlanto-axial rotatory fixation (AORF develops on the background of acute torticollis. Widely adopted terms such as C1 subluxation or atlantooccipital rotational subluxation do not reflect the core of this pathology and carry negative weight in the diagnostics and treatment of AORF. Retrospective analysis of the diagnostics and treatment outcome of 5 children with confirmed AORF diagnosis and literature review were performed. Clinical method, radiography and functional computer tomography were used to verify the diagnosis. De-rotational halo-traction and open correction with screw fixation were applied for treatment. Head position was managed to be improved in all patients. In one case the reduction was performed using correction in suboccipital segments and in other 4 cases the correction and fixation by Harms and de-rotational halo-traction allowed to correct torticollis. The pain syndrome had been arrested completely. Disease outcome resulted in formation of C1-C2 fibrous or bone fusion regardless the method of treatment. The patients with neglected AORF represent a great challenge for diagnostics and treatment. When conservative treatment fails it is necessary to involve de-rotational halo-traction with possible application of open reduction and posterior fusion. The purpose of treatment is to eliminate torticollis and pain using creation of proper C1-C2 alignment. The motions in atlantooccipital joint do not restore due to formation of the fibrous or bone fusion.

  11. [Domestic external fixator application in the treatment of limb deformities: 7 289 cases application report].

    Science.gov (United States)

    Qin, S H; Guo, B F; Zheng, X J; Jiao, S F; Xia, H T; Peng, A M; Pan, Q; Zang, J C; Wang, Z J

    2017-09-01

    Objective: To discuss the clinical application and effects of domestic external fixator in the treatment of patients with malformations of limbs. Methods: A total of 7 289 patients with malformation of limbs who had been operated in Qin Sihe orthopedic surgery team from January 1989 to June 2016 were retrospective analyzed. The patients were treated with domestic external fixator, including 4 033 males and 3 256 females, aging from 2 to 82 years with a mean age of 23.4 years. There were 2 732 patients using Ilizarov external fixator, 4 713 patients using hybrid external fixator, 57 patients using monobrachial external fixator, 232 patients using Ilizarov external fixator and hybrid external fixator. The Ilizarov, hybrid and monobrachial external fixator were used in 67, 65 and 0 patients on the upper limbs and in 2 665, 4 616 and 57 patients on the lower limbs. There were 3 028 patients operated on the left limbs, 3 260 patients operated on the right limbs and 1 001 patients operated on the bilateral limbs. The top three types of diseases were sequelae of poliomyelitis, cerebral palsy and post-traumatic stress disorder peromely. Deformity types inclued talipes equinovarus, knee flexion deformity, cavus foot and so on. Results: All the patients were followed up for a period of 2.5 months to 22.4 years, with an average follow-up time of 5.4 years. All of the external fixators were used for single once, and there was no substitute for external fixator quality problem. All the patients were completed surgery goal until removing external fixation except 1 patient gave up treatment and 1 removed the fixator because of metal allergy. The common complications included wire or pin infection and joint movement limitation and so on. Conclusions: The domestic external fixator developed and produced based on the characteristics of Chinese limb deformity disability. The domestic external fixator can be used to treat kinds of limb deformities with the advantages of practical

  12. Tailings treatment techniques for uranium mill waste: a review of existing information

    International Nuclear Information System (INIS)

    Sherwood, D.R.; Serne, R.J.

    1983-07-01

    Of primary concern at uranium mill sites in the United States is the potential of ground-water contamination from mill wastes that are disposed in tailings impoundments. Although many systems have been used to control seepage from tailings impoundments, most of these systems are limited in their ability to handle an excess of tailings solution. Three general amelioration methods were identified: neutralization, fixation and specific constituent removal. During neutralization, a reagent is added to the tailings solution to neutralize the acidity and raise the pH to reduce the solubility of various pH sensitive contaminants. Fixation processes add materials such as lime, cement or asphalt to the waste to produce a physically stable composition that resists leaching of hazardous constituents. Specific constituent removal encompasses varying techniques, such as alternate ore leaching processes, effluent treatment with sorption, or ion exchange agents or selected precipitation that reduce specific constituent concentrations in tailings solution. Neutralization processes appear to be best suited for treating uranium mill tailings because they can, at a reasonable cost, limit the solution concentration of many contaminants. The effectiveness of the process depends on the reagent used as well as the waste being treated. Of the six reagents studied (lime, limestone, caustic soda, soda ash, combined limestone/lime and combined alumina/lime/soda), a combined treatment of limestone and lime seems best, especially for tailings containing ferric iron as the limestone economically buffers the solution acidity while the lime takes the pH to 8.0, an optimum level for heavy metal removal. For those tailings containing ferrous iron, lime alone works best. The costs for the lime/limestone or lime processes range from $0.20 to $1.00 per 1000 gal of treated water, excluding capital equipment costs

  13. Treatment of Unicameral Bone Cysts of the Proximal Femur With Internal Fixation Lessens the Risk of Additional Surgery.

    Science.gov (United States)

    Wilke, Benjamin; Houdek, Matthew; Rao, Rameshwar R; Caird, Michelle S; Larson, A Noelle; Milbrandt, Todd

    2017-09-01

    Little data exist to guide the treatment of unicameral bone cysts in the proximal femur. Methods of treatment include corticosteroid injections, curettage and bone grafting, and internal fixation. The authors completed a multi-institutional, retrospective review to evaluate their experience with proximal femoral unicameral bone cysts. They posed the following questions: (1) Does internal fixation reduce the risk of further procedures for the treatment of a unicameral bone cyst? (2) Is radiographic healing faster with internal fixation? Following institutional review board approval, the authors conducted a retrospective review of 36 patients treated for a unicameral bone cyst of the proximal femur at their institutions between 1974 and 2014. Medical records and radiographs were reviewed to identify patient demographics and treatment outcomes. Tumor locations included femoral neck (n=13), intertrochanteric (n=16), and subtrochanteric (n=7). Initial treatment included steroid injection (n=2), curettage and bone grafting (n=9), and internal fixation with curettage and bone grafting (n=25). Mean time was 9 months to radiographic healing and 15 months to return to full activity. The number of patients requiring additional surgeries was increased among those who did not undergo internal fixation. There was no difference in time to radiographic healing. However, time to return to normal activities was reduced if patients had received internal fixation. A significant reduction in additional procedures was observed when patients had been treated with internal fixation. Although this did not influence time to radiographic healing, patients did return to normal activities sooner. Internal fixation should be considered in the treatment of proximal femoral unicameral bone cysts. [Orthopedics. 2017; 40(5):e862-e867.]. Copyright 2017, SLACK Incorporated.

  14. Thermal plasma waste treatment

    International Nuclear Information System (INIS)

    Heberlein, Joachim; Murphy, Anthony B

    2008-01-01

    Plasma waste treatment has over the past decade become a more prominent technology because of the increasing problems with waste disposal and because of the realization of opportunities to generate valuable co-products. Plasma vitrification of hazardous slags has been a commercial technology for several years, and volume reduction of hazardous wastes using plasma processes is increasingly being used. Plasma gasification of wastes with low negative values has attracted interest as a source of energy and spawned process developments for treatment of even municipal solid wastes. Numerous technologies and approaches exist for plasma treatment of wastes. This review summarizes the approaches that have been developed, presents some of the basic physical principles, provides details of some specific processes and considers the advantages and disadvantages of thermal plasmas in waste treatment applications. (topical review)

  15. Treatment strategies for transuranic wastes

    International Nuclear Information System (INIS)

    Schneider, K.J.; Ross, W.A.; Swanson, J.L.; Allen, R.P.; Yasutake, K.M.

    1986-01-01

    This paper presents an analysis of treatment options or strategies for transuranic wastes expected to be generated at a commercial nuclear fuel reprocessing plant. Six potential options were analyzed, ranging from no treatment to maximum volume reduction and high quality waste forms. Economics for the total management of these wastes (treatment, transportation, disposal) indicate life-cycle savings for extensive treatment are as high as $1.7 billion for 70,000 MTU. Evaluations of the waste processing and waste forms support the selection of a number of the extensive waste treatments. It is concluded that there are significant incentives for extensive treatment of transuranic wastes

  16. Polymeric media for tritium fixation. Supplement I

    International Nuclear Information System (INIS)

    Franz, J.A.; Burger, L.L.

    1976-01-01

    Procedures for the fixation of tritium as TH or THO in two different polymeric media are described. The complete procedure for THO fixation in a polyureylene-polyurethane polumer, including polymer molding procedures and leach tests is presented. The catalytic tritiation of polystyrene under very mild conditions using a rhodium catalyst is also described. Thermal stabilities and cost estimates for the polymers examined under this program are discussed. Organic polymers were found to have attractive features for the fixation and storage of concentrated tritium wastes due to the convenience of fixation procedures and favorable properties of the resulting media

  17. Treatment strategies for transuranic wastes

    International Nuclear Information System (INIS)

    Schneider, K.J.; Swanson, J.L.; Ross, W.A.; Allen, R.P.; Yasutake, K.M.

    1986-01-01

    This paper presents an analysis of treatment options or strategies for transuranic wastes expected to be generated at a commercial nuclear fuel reprocessing plant. Six potential options were analyzed, ranging from no treatment to maximum volume reduction and high quality waste forms. Economics for the total management of these (treatment, transportation, disposal) indicate life-cycle savings for extensive treatment are as high as $1.7 billion for 70,000 MTU. Evaluations of the waste processing and waste forms support the selection of a number of the extensive waste treatments. It is concluded that there are significant incentives for extensive treatment of transuranic wastes

  18. Waste treatment plant

    International Nuclear Information System (INIS)

    Adesanmi, C.A

    2009-01-01

    Waste Treatment Plant (WTP) is designed to provide appropriate systems for processing, immobilization and storage of low and medium radioactive waste arising from the operation of the research facilities of the Nuclear Technology Centre (NTC). It will serve as central collection station processing active waste generated through application of radionuclide in science, medicine and industry in the country. WTP building and structures will house the main waste processing systems and supporting facilities. All facilities will be interconnected. The interim storage building for processed waste drums will be located separately nearby. The separate interim storage building is located near the waste treatment building. Considering the low radiation level of the waste, storage building is large with no solid partitioning walls and with no services or extra facilities other than lighting and smoke alarm sensors. The building will be designed such that drums(200-1)are stacked 3 units high using handling by fork lift truck. To prevent radiation exposure to on-site personnel, the interim storage building will be erected apart from waste treatment plant or other buildings. The interim storage building will also be ready for buffer storage of unconditioned waste waiting for processing or decay and for storage material from the WTP

  19. Handling and treatment of low-level radioactive wastes from gaseous diffusion plants in the United States of America

    International Nuclear Information System (INIS)

    Wing, J.F.; Behrend, J.E.

    1984-01-01

    Gaseous diffusion plants in the United States of America currently generate very small quantities of low-level radioactive wastes. These wastes consist primarily of airborne effluent solid trapping media and liquid scrubber solutions, liquid effluent treatment sludges, waste oils and solvents, scrap metals and conventional combustible wastes such as floor sweepings, cleaning rags and shoe covers. In addition to waste emanating from current operations, large quantities of scrap metal generated during the Cascade Improvement Program are stored above ground at each of the diffusion plants. The radionuclides of primary concern are uranium and 99 Tc. Current radioactive waste treatment consists of uranium dissolution in weak acids followed by chemical precipitation and/or solvent extraction for uranium recovery. Current disposal operations consist of above ground storage of scrap metals, shallow land burial of inorganic solids and incineration of combustible wastes. With increased emphasis on reducing the potential for off-site radiological dose, several new treatment and disposal options are being studied and new projects are being planned. One project of particular interest involves the installation of a high temperature incinerator to thermally degrade hazardous organic wastes contaminated with low-level radioactive wastes. Other technologies being studied include fixation of uranium-bearing sludges in concrete before burial, decontamination of scrap metals by smelting and use of specially engineered centralized burial grounds. (author)

  20. Waste treatment

    International Nuclear Information System (INIS)

    Hutson, G.V.

    1996-01-01

    Numerous types of waste are produced by the nuclear industry ranging from high-level radioactive and heat-generating, HLW, to very low-level, LLW and usually very bulky wastes. These may be in solid, liquid or gaseous phases and require different treatments. Waste management practices have evolved within commercial and environmental constraints resulting in considerable reduction in discharges. (UK)

  1. [Comparison of external fixation with or without limited internal fixation for open knee fractures].

    Science.gov (United States)

    Li, K N; Lan, H; He, Z Y; Wang, X J; Yuan, J; Zhao, P; Mu, J S

    2018-03-01

    Objective: To explore the characteristics and methods of different fixation methods and prevention of open knee joint fracture. Methods: The data of 86 cases of open knee joint fracture admitted from January 2002 to December 2015 in Department of Orthopaedics, Affiliated Hospital of Chengdu University were analyzed retrospectively.There were 65 males and 21 females aged of 38.6 years. There were 38 cases treated with trans articular external fixation alone, 48 cases were in the trans articular external fixation plus auxiliary limited internal fixation group. All the patients were treated according to the same three stages except for different fixation methods. Observation of external fixation and fracture fixation, fracture healing, wound healing and treatment, treatment and related factors of infection control and knee function recovery. χ(2) test was used to analyze data. Results: Eleven patients had primary wound healing, accounting for 12.8%. Seventy-five patients had two wounds healed, accounting for 87.2%. Only 38 cases of trans articular external fixator group had 31 cases of articular surface reduction, accounting for 81.6%; Five cases of trans articular external fixator assisted limited internal fixation group had 5 cases of poor reduction, accounting for 10.4%; There was significant difference between the two groups (χ(2)=44.132, P external fixation group, a total of 23 cases of patients with infection, accounted for 60.5% of external fixation group; trans articular external fixation assisted limited internal fixation group there were 30 cases of patients with infection, accounting for the assistance of external fixator and limited internal fixation group 62.5%; There was significant difference between the two groups(χ(2)=0.035, P >0.05). Five cases of fracture nonunion cases of serious infection, patients voluntarily underwent amputation. The Lysholm Knee Scale: In the external fixation group, 23 cases were less than 50 points, accounting for 60

  2. WASTE TREATMENT BUILDING SYSTEM DESCRIPTION DOCUMENT

    Energy Technology Data Exchange (ETDEWEB)

    F. Habashi

    2000-06-22

    The Waste Treatment Building System provides the space, layout, structures, and embedded subsystems that support the processing of low-level liquid and solid radioactive waste generated within the Monitored Geologic Repository (MGR). The activities conducted in the Waste Treatment Building include sorting, volume reduction, and packaging of dry waste, and collecting, processing, solidification, and packaging of liquid waste. The Waste Treatment Building System is located on the surface within the protected area of the MGR. The Waste Treatment Building System helps maintain a suitable environment for the waste processing and protects the systems within the Waste Treatment Building (WTB) from most of the natural and induced environments. The WTB also confines contaminants and provides radiological protection to personnel. In addition to the waste processing operations, the Waste Treatment Building System provides space and layout for staging of packaged waste for shipment, industrial and radiological safety systems, control and monitoring of operations, safeguards and security systems, and fire protection, ventilation and utilities systems. The Waste Treatment Building System also provides the required space and layout for maintenance activities, tool storage, and administrative facilities. The Waste Treatment Building System integrates waste processing systems within its protective structure to support the throughput rates established for the MGR. The Waste Treatment Building System also provides shielding, layout, and other design features to help limit personnel radiation exposures to levels which are as low as is reasonably achievable (ALARA). The Waste Treatment Building System interfaces with the Site Generated Radiological Waste Handling System, and with other MGR systems that support the waste processing operations. The Waste Treatment Building System interfaces with the General Site Transportation System, Site Communications System, Site Water System, MGR

  3. WASTE TREATMENT BUILDING SYSTEM DESCRIPTION DOCUMENT

    International Nuclear Information System (INIS)

    Habashi, F.

    2000-01-01

    The Waste Treatment Building System provides the space, layout, structures, and embedded subsystems that support the processing of low-level liquid and solid radioactive waste generated within the Monitored Geologic Repository (MGR). The activities conducted in the Waste Treatment Building include sorting, volume reduction, and packaging of dry waste, and collecting, processing, solidification, and packaging of liquid waste. The Waste Treatment Building System is located on the surface within the protected area of the MGR. The Waste Treatment Building System helps maintain a suitable environment for the waste processing and protects the systems within the Waste Treatment Building (WTB) from most of the natural and induced environments. The WTB also confines contaminants and provides radiological protection to personnel. In addition to the waste processing operations, the Waste Treatment Building System provides space and layout for staging of packaged waste for shipment, industrial and radiological safety systems, control and monitoring of operations, safeguards and security systems, and fire protection, ventilation and utilities systems. The Waste Treatment Building System also provides the required space and layout for maintenance activities, tool storage, and administrative facilities. The Waste Treatment Building System integrates waste processing systems within its protective structure to support the throughput rates established for the MGR. The Waste Treatment Building System also provides shielding, layout, and other design features to help limit personnel radiation exposures to levels which are as low as is reasonably achievable (ALARA). The Waste Treatment Building System interfaces with the Site Generated Radiological Waste Handling System, and with other MGR systems that support the waste processing operations. The Waste Treatment Building System interfaces with the General Site Transportation System, Site Communications System, Site Water System, MGR

  4. Ball-joint versus single monolateral external fixators for definitive treatment of tibial shaft fractures.

    Science.gov (United States)

    Beltsios, Michail; Mavrogenis, Andreas F; Savvidou, Olga D; Karamanis, Eirineos; Kokkalis, Zinon T; Papagelopoulos, Panayiotis J

    2014-07-01

    To compare modular monolateral external fixators with single monolateral external fixators for the treatment of open and complex tibial shaft fractures, to determine the optimal construct for fracture union. A total of 223 tibial shaft fractures in 212 patients were treated with a monolateral external fixator from 2005 to 2011; 112 fractures were treated with a modular external fixator with ball-joints (group A), and 111 fractures were treated with a single external fixator without ball-joints (group B). The mean follow-up was 2.9 years. We retrospectively evaluated the operative time for fracture reduction with the external fixator, pain and range of motion of the knee and ankle joints, time to union, rate of malunion, reoperations and revisions of the external fixators, and complications. The time for fracture reduction was statistically higher in group B; the rate of union was statistically higher in group B; the rate of nonunion was statistically higher in group A; the mean time to union was statistically higher in group A; the rate of reoperations was statistically higher in group A; and the rate of revision of the external fixator was statistically higher in group A. Pain, range of motion of the knee and ankle joints, rates of delayed union, malunion and complications were similar. Although modular external fixators are associated with faster intraoperative fracture reduction with the external fixator, single external fixators are associated with significantly better rates of union and reoperations; the rates of delayed union, malunion and complications are similar.

  5. Stress and stability of plate-screw fixation and screw fixation in the treatment of Schatzker type IV medial tibial plateau fracture: a comparative finite element study.

    Science.gov (United States)

    Huang, Xiaowei; Zhi, Zhongzheng; Yu, Baoqing; Chen, Fancheng

    2015-11-25

    The purpose of this study is to compare the stress and stability of plate-screw fixation and screw fixation in the treatment of Schatzker type IV medial tibial plateau fracture. A three-dimensional (3D) finite element model of the medial tibial plateau fracture (Schatzker type IV fracture) was created. An axial force of 2500 N with a distribution of 60% to the medial compartment was applied to simulate the axial compressive load on an adult knee during single-limb stance. The equivalent von Mises stress, displacement of the model relative to the distal tibia, and displacement of the implants were used as the output measures. The mean stress value of the plate-screw fixation system was 18.78 MPa, which was significantly (P stress value of the triangular fragment in the plate-screw fixation system model was 42.04 MPa, which was higher than that in the screw fixation model (24.18 MPa). But the mean stress of the triangular fractured fragment in the screw fixation model was significantly higher in terms of equivalent von Mises stress (EVMS), x-axis, and z-axis (P < 0.001). This study demonstrated that the load transmission mechanism between plate-screw fixation system and screw fixation system was different and the stability provided by the plate-screw fixation system was superior to the screw fixation system.

  6. External fixation combined with delayed internal fixation in treatment of tibial plateau fractures with dislocation.

    Science.gov (United States)

    Tao, Xingguang; Chen, Nong; Pan, Fugen; Cheng, Biao

    2017-10-01

    The aim of this study was to evaluate the clinical efficacy of external fixation, delayed open reduction, and internal fixation in treating tibial plateau fracture with dislocation.Clinical data of 34 patients diagnosed with tibial plateau fracture complicated with dislocation between January 2009 and May 2015 were retrospectively analyzed. Fifteen patients in group A underwent early calcaneus traction combined with open reduction and internal fixation and 19 in group B received early external fixation combined with delayed open reduction and internal fixation. Operation time, postoperative complication, bone healing time, knee joint range of motion, initial weight-bearing time, Rasmussen tibial plateau score, and knee function score (HSS) were statistically compared between 2 groups.The mean follow-up time was 18.6 months (range: 5-24 months). The mean operation time in group A was 96 minutes, significantly longer than 71 minutes in group B (P  .05). In group A, initial weight-bearing time in group A was (14.0 ± 3.6) weeks, significantly differing from (12.9 ± 2.8) weeks in group B (P  0.05). Rasmussen tibial plateau score in group A was slightly lower than that in group B (P > .05). The excellent rate of knee joint function in group A was 80% and 84.21% in group B (P > .05).External fixation combined with delayed open reduction and internal fixation is a safer and more efficacious therapy of tibial plateau fracture complicated with dislocation compared with early calcaneus traction and open reduction and internal fixation.

  7. Analysis of waste treatment requirements for DOE mixed wastes: Technical basis

    International Nuclear Information System (INIS)

    1995-02-01

    The risks and costs of managing DOE wastes are a direct function of the total quantities of 3wastes that are handled at each step of the management process. As part of the analysis of the management of DOE low-level mixed wastes (LLMW), a reference scheme has been developed for the treatment of these wastes to meet EPA criteria. The treatment analysis in a limited form was also applied to one option for treatment of transuranic wastes. The treatment requirements in all cases analyzed are based on a reference flowsheet which provides high level treatment trains for all LLMW. This report explains the background and basis for that treatment scheme. Reference waste stream chemical compositions and physical properties including densities were established for each stream in the data base. These compositions are used to define the expected behavior for wastes as they pass through the treatment train. Each EPA RCRA waste code was reviewed, the properties, chemical composition, or characteristics which are of importance to waste behavior in treatment were designated. Properties that dictate treatment requirements were then used to develop the treatment trains and identify the unit operations that would be included in these trains. A table was prepared showing a correlation of the waste physical matrix and the waste treatment requirements as a guide to the treatment analysis. The analysis of waste treatment loads is done by assigning wastes to treatment steps which would achieve RCRA compliant treatment. These correlation's allow one to examine the treatment requirements in a condensed manner and to see that all wastes and contaminant sets are fully considered

  8. Monosegmental fixation for the treatment of fractures of the thoracolumbar spine

    Directory of Open Access Journals (Sweden)

    Defino Helton

    2007-01-01

    Full Text Available Background : A short vertebral arthrodesis has been one of the objectives of the surgical treatment of fractures of the thoracolumbar spine. We present here clinical, functional and radiographic outcome obtained after monosegmental fixation (single posterior or combined anterior and posterior of specific types of unstable thoracolumbar fractures. Materials and Methods : Twenty four patients with fractures of the thoracolumbar spine submitted to monosegmental surgical treatment (Group I - 18 single posterior monosegmental fixations and Group II - 6 combined anterior and posterior fixations were retrospectively evaluated according to clinical, radiographic and functional parameters. The indication for surgery was instability or neurological deficit. All the procedures were indicated and performed by the senior surgeon (Helton LA Defino. Results : The patients from group I were followed-up from 2 to 12 years (mean: 6.65±2.96. The clinical, functional and radiographic results show that a single posterior monosegmental fixation is adequate and a satisfactory procedure to be used in specific types of thoracolumbar spine fractures, The patients from group II were followed-up from 9 to 15 years (mean: 13 ± 2,09 years. On group II the results of clinical evaluation showed moderate indices of residual pain and of satisfaction with the final result. The values obtained by functional evaluation showed that 66.6% of the patients were unable to return to their previous job and presented a moderate disability index (Oswestry = 16.6 and a significant reduction of quality of life based on the SF-36 questionnaire. Radiographic evaluation showed increased kyphosis of the fixed vertebral segment during the late postoperative period, accompanied by a reduction of the height of the intervertebral disk. Conclusion : It is possible to stabilize the fractures which have an anterior good load-bearing capacity by a standalone posterior monosegmental fixation. However

  9. Soybean seed treatment with nickel improves biological nitrogen fixation and urease activity

    Directory of Open Access Journals (Sweden)

    José eLavres Junior

    2016-05-01

    Full Text Available Nickel (Ni is an essential micronutrient required for plants’ metabolism due to its role as a structural component of urease and hydrogenase, which in turn perform nitrogen (N metabolism in many legume species. Seed treatment with cobalt, molybdenum and Bradyrhizobium strains has been widely practiced to improve crops. Additionally, seed treatment together with Ni fertilization of soybean might improve the efficiency of biological nitrogen fixation (BNF, boosting grain dry matter yield and N content. The objective of this study was to evaluate the effect of soybean seed treatment with Ni rates (0, 45, 90,135, 180, 360 and 540 mg kg-1 on biological nitrogen fixation (BNF, directly by the 15N natural abundance method (δ15N‰ and by measurement of urease [E.C. 3.5.1.5] activity, as well as indirectly by nitrogenase (N-ase activity [E.C. 1.18.6.1]. Soybean plants (cultivar BMX Potência RR were grown in a sandy soil up to the R7 developmental stage (grain maturity, at which point the nutrient content in the leaves, chlorophyll content, urease and N-ase activities, Ni and N content in the grains, nodulation (at R1 - flowering stage, as well as the contribution of biological nitrogen fixation (δ15N ‰, were evaluated. The proportion of N derived from N2 fixation varied from 77 to 99% using the natural 15N abundance method and non-nodulating Panicum miliaceum and Phalaris canariensis as references. A Ni rate of 45 mg kg-1 increased BNF by 12% compared to the control. The increased N uptake in the grains was closely correlated with chlorophyll content in the leaves, urease and N-ase activities, as well as with nodulation. Grain dry matter yield and aerial part dry matter yield increased, respectively, by 84% and 51% in relation to the control plants at 45 mg kg-1 Ni via seed treatment. Despite, Ni concentration was increased with Ni-seed treatment, Ni rates higher than 135 mg kg-1 promoted negative effects on plant growth and yield. In these

  10. Surrogate formulations for thermal treatment of low-level mixed waste, Part II: Selected mixed waste treatment project waste streams

    Energy Technology Data Exchange (ETDEWEB)

    Bostick, W.D.; Hoffmann, D.P.; Chiang, J.M.; Hermes, W.H.; Gibson, L.V. Jr.; Richmond, A.A. [Martin Marietta Energy Systems, Inc., Oak Ridge, TN (United States); Mayberry, J. [Science Applications International Corp., Idaho Falls, ID (United States); Frazier, G. [Univ. of Tennessee, Knoxville, TN (United States)

    1994-01-01

    This report summarizes the formulation of surrogate waste packages, representing the major bulk constituent compositions for 12 waste stream classifications selected by the US DOE Mixed Waste Treatment Program. These waste groupings include: neutral aqueous wastes; aqueous halogenated organic liquids; ash; high organic content sludges; adsorbed aqueous and organic liquids; cement sludges, ashes, and solids; chloride; sulfate, and nitrate salts; organic matrix solids; heterogeneous debris; bulk combustibles; lab packs; and lead shapes. Insofar as possible, formulation of surrogate waste packages are referenced to authentic wastes in inventory within the DOE; however, the surrogate waste packages are intended to represent generic treatability group compositions. The intent is to specify a nonradiological synthetic mixture, with a minimal number of readily available components, that can be used to represent the significant challenges anticipated for treatment of the specified waste class. Performance testing and evaluation with use of a consistent series of surrogate wastes will provide a means for the initial assessment (and intercomparability) of candidate treatment technology applicability and performance. Originally the surrogate wastes were intended for use with emerging thermal treatment systems, but use may be extended to select nonthermal systems as well.

  11. Surrogate formulations for thermal treatment of low-level mixed waste, Part II: Selected mixed waste treatment project waste streams

    International Nuclear Information System (INIS)

    Bostick, W.D.; Hoffmann, D.P.; Chiang, J.M.; Hermes, W.H.; Gibson, L.V. Jr.; Richmond, A.A.; Mayberry, J.; Frazier, G.

    1994-01-01

    This report summarizes the formulation of surrogate waste packages, representing the major bulk constituent compositions for 12 waste stream classifications selected by the US DOE Mixed Waste Treatment Program. These waste groupings include: neutral aqueous wastes; aqueous halogenated organic liquids; ash; high organic content sludges; adsorbed aqueous and organic liquids; cement sludges, ashes, and solids; chloride; sulfate, and nitrate salts; organic matrix solids; heterogeneous debris; bulk combustibles; lab packs; and lead shapes. Insofar as possible, formulation of surrogate waste packages are referenced to authentic wastes in inventory within the DOE; however, the surrogate waste packages are intended to represent generic treatability group compositions. The intent is to specify a nonradiological synthetic mixture, with a minimal number of readily available components, that can be used to represent the significant challenges anticipated for treatment of the specified waste class. Performance testing and evaluation with use of a consistent series of surrogate wastes will provide a means for the initial assessment (and intercomparability) of candidate treatment technology applicability and performance. Originally the surrogate wastes were intended for use with emerging thermal treatment systems, but use may be extended to select nonthermal systems as well

  12. Treatment of neglected elbow dislocations with the help of hinged external fixator: Report of two cases

    Directory of Open Access Journals (Sweden)

    Özgür Karakoyun

    2014-06-01

    Full Text Available Elbow dislocations are cases that have to be treated in emergency conditions. Neglected elbow dislocations are seen very rarely and the treatment of such cases are more complicated than acute cases. We present two cases of neglected elbow dislocations treated with open reduction and hinged external fixators. Case 1: 23 year old female patient had a neglected posterior dislocation of left elbow with ipsilateral humeral shaft fracture caused by car accident. The patient was treated after 3 months of initial trauma. We have performed open reduction for the joint. After that we fixed the joint whit a hinged external fixator. The humeral shaft fracture was also fixed with the components of the external fixator. Case 2: 33 year male patient had a large bone and soft tissue defect around the left elbow accompanying with neglected medial elbow dislocation. He presented to our clinic with a delay of 2 months. The patient was treated with open reduction and hinged external fixator after reconstruction of bone defect of distal humerus. Conclusion: The treatment of neglected cases is quite challenging. Open reduction and external fixation has satisfactory results in treatment of late cases of elbow dislocation with the possibility of early rehabilitation. This method can be considered as an option for such cases. J Clin Exp Invest 2014; 5 (2: 443-446

  13. Comparison of screw fixation with elastic fixation methods in the treatment of syndesmosis injuries in ankle fractures.

    Science.gov (United States)

    Seyhan, Mustafa; Donmez, Ferdi; Mahirogullari, Mahir; Cakmak, Selami; Mutlu, Serhat; Guler, Olcay

    2015-07-01

    17 patients with ankle syndesmosic injury were treated with a 4.5mm single cortical screw fixation (passage of screw 4 cortices) and 15 patients were treated with single-level elastic fixation material. All patients were evaluated according to the AOFAS ankle and posterior foot scale at the third, sixth and twelfth months after the fixation. The ankle range of movement was recorded together with the healthy side. The Student's t test was used for statistical comparisons. No statistical significant difference was observed between the AOFAS scores (p>0.05). The range of dorsiflexion and plantar flexion motion of the elastic fixation group at the 6th and 12th months were significantly better compared to the screw fixation group (pankle syndesmosis injuries. The unnecessary need of a second surgical intervention for removal of the fixation material is another advantageous aspect of this method of fixation. Copyright © 2015. Published by Elsevier Ltd.

  14. SECONDARY WASTE MANAGEMENT STRATEGY FOR EARLY LOW ACTIVITY WASTE TREATMENT

    Energy Technology Data Exchange (ETDEWEB)

    TW, CRAWFORD

    2008-07-17

    This study evaluates parameters relevant to River Protection Project secondary waste streams generated during Early Low Activity Waste operations and recommends a strategy for secondary waste management that considers groundwater impact, cost, and programmatic risk. The recommended strategy for managing River Protection Project secondary waste is focused on improvements in the Effiuent Treatment Facility. Baseline plans to build a Solidification Treatment Unit adjacent to Effluent Treatment Facility should be enhanced to improve solid waste performance and mitigate corrosion of tanks and piping supporting the Effiuent Treatment Facility evaporator. This approach provides a life-cycle benefit to solid waste performance and reduction of groundwater contaminants.

  15. Minimally invasive treatment of tibial pilon fractures through arthroscopy and external fixator-assisted reduction.

    Science.gov (United States)

    Luo, Huasong; Chen, Liaobin; Liu, Kebin; Peng, Songming; Zhang, Jien; Yi, Yang

    2016-01-01

    The aim of this study was to evaluate the clinical outcome of tibial pilon fractures treated with arthroscopy and assisted reduction with an external fixator. Thirteen patients with tibial pilon fractures underwent assisted reduction for limited lower internal fixation with an external fixator under arthroscopic guidance. The weight-bearing time was decided on the basis of repeat radiography of the tibia 3 months after surgery. Postoperative ankle function was evaluated according to the Mazur scoring system. Healing of fractures was achieved in all cases, with no complications such as severe infection, skin necrosis, or an exposed plate. There were 9 excellent, 2 good, and 2 poor outcomes, scored according to the Mazur system. The acceptance rate was 85%. Arthroscopy and external fixator-assisted reduction for the minimally invasive treatment of tibial pilon fractures not only produced less trauma but also protected the soft tissues and blood supply surrounding the fractures. External fixation could indirectly provide reduction and effective operative space for arthroscopic implantation, especially for AO type B fractures and partial AO type C1 fractures.

  16. Treatment of solid non-active wastes

    International Nuclear Information System (INIS)

    Chmielewska, E.

    2008-01-01

    In this part of the text-book treatment of solid non-active wastes is described. This part consist of following chapters: (1) Law on wastes; (2) Present situation in waste management; (3) Strategic tendencies of waste management; (4) Incineration (disposal of solid wastes); (5) Disposal; (6) Composting; (7) Treatment of sludge from sewage clarification plant; (8) Biodegradation; (9) Recycling of wastes (assessing of secondary raw materials). Legal aspects of treatment of solid non-active wastes is presented

  17. [Internal fixation treatment of multiple rib fractures with absorbable rib-connecting-pins under epidural anesthesia].

    Science.gov (United States)

    Liu, Jinliang; Li, Keyao; Ju, Zhenlong; Bai, Yan

    2011-03-01

    To study the indications, methods and experience of absorbable rib-connecting-pins fixation in the treatment of multiple rib fractures. 52 cases with multiple rib fractures were performed internal fixation with absorbable rib-connecting-pins under epidural anesthesia. All cases were followed up for 1 to 12 months, with an average of 5 months. All fractures were achieved healing in 3 to 6 months after the operation and were not found chest wall deformity. Absorbable rib-connecting-pins fixation is a simple and effective method and worthies recommending to perform operation for the appropriate cases with multiple rib fractures.

  18. Thermal treatment of organic radioactive waste

    International Nuclear Information System (INIS)

    Chrubasik, A.; Stich, W.

    1993-01-01

    The organic radioactive waste which is generated in nuclear and isotope facilities (power plants, research centers and other) must be treated in order to achieve a waste form suitable for long term storage and disposal. Therefore the resulting waste treatment products should be stable under influence of temperature, time, radioactivity, chemical and biological activity. Another reason for the treatment of organic waste is the volume reduction with respect to the storage costs. For different kinds of waste, different treatment technologies have been developed and some are now used in industrial scale. The paper gives process descriptions for the treatment of solid organic radioactive waste of low beta/gamma activity and alpha-contaminated solid organic radioactive waste, and the pyrolysis of organic radioactive waste

  19. Low-level-waste-treatment handbook

    International Nuclear Information System (INIS)

    Clinton, S.D.; Goeller, H.E.; Holladay, D.W.; Donaldson, T.L.

    1982-01-01

    The initial draft of the Low-Level Waste Treatment Handbook has been prepared and submitted to the DOE Low-Level Waste Management Program for review and comment. A revised draft is scheduled to be delivered to DOE Headquarters in December 1982. The Handbook is designed to be useful to all individuals and groups concerned with low-level wastes. It is one of several volumes that will ultimately comprise a Low-Level Waste Technology Handbook. The objective of the Low-Level Waste Treatment Handbook is to present an overview of current practices related to the segregation, classification, volume reduction, solidification, handling, packaging, and transportation of LLW for disposal in a shallow land burial facility. The Handbook is intended to serve as a guide to individuals interested in the treatment and handling of low-level radioactive waste. The Handbook will not explicitly tell the user how to design and operate LLW treatment facilities, but rather will identify (1) kinds of information required to evaluate the options, (2) methods that may be used to evaluate these options, and (3) limitations associated with the selection of the treatment options. The focus of the Handbook is providing guidance on how to do waste treatment for disposal by shallow land burial

  20. A financial analysis of maxillomandibular fixation versus rigid internal fixation for treatment of mandibular fractures.

    Science.gov (United States)

    Schmidt, B L; Kearns, G; Gordon, N; Kaban, L B

    2000-11-01

    The aim of this study was to compare the cost-effectiveness of mandibular fracture treatment by closed reduction with maxillomandibular fixation (CRF) with open reduction and rigid internal fixation (ORIF). This was a retrospective study of 85 patients admitted to the Oral and Maxillofacial Surgery Service at San Francisco General Hospital and treated for mandibular fractures from January 1 to December 31, 1993. The patients were divided into 2 groups: 1) those treated with CRF and 2) those treated with ORIF. The outcome variables were length of hospital stay, duration of anesthesia, and time in operating room. The charge for primary fracture treatment included the fees for the operation and hospitalization without any complications. Within the group of 85 patients treated for mandibular fractures in 1993, 10 patients treated with CRF and 10 patients treated with ORIF were randomly selected, and hospital billing statements were used to estimate the average charge of primary treatment. The average charge to manage a major postoperative infection also was estimated based on the billing statements of 10 randomly selected patients treated in 1992 (5 treated with CRF, 5 with ORIF) who required hospital admission for the management of a complication. The average total charge was computed by using the average charge for primary treatment plus the incidence of postoperative infection multiplied by the average charge for management of that complication. Eighty-five patients were included in the study. The average charge for primary treatment was $10,100 for the CRF group and $28,362 for the ORIF group. The average charge for the inpatient management of a major postoperative infection was $26,671 for the CRF group and $39,213 for the ORIF group. The average total charge for management of a mandible fracture with CRF was $10,927; the total charge for the ORIF group was $34,636. The results of this retrospective study suggest that the use of CRF in the management of mandibular

  1. The Hybrid Treatment Process for mixed radioactive and hazardous waste treatment

    International Nuclear Information System (INIS)

    Ross, W.A.; Kindle, C.H.

    1992-06-01

    This paper describes a new process for treating mixed hazardous and radioactive waste, commonly called mixed waste. The process is called the Hybrid Treatment Process (HTP), so named because it is built on the 20 years of experience with vitrification of wastes in melters, and the 12 years of experience with treatment of wastes by the in situ vitrification (ISV) process. It also uses techniques from several additional technologies. Mixed wastes are being generated by both the US Department of Energy (DOE) and by commercial sources. The wastes are those that contain both a hazardous waste regulated under the US Environmental Protection Agency's (EPA) Resource, Conservation, and Recovery Act (RCRA) regulations and a radioactive waste with source, special nuclear, or byproduct materials. The dual regulation of the wastes increases the complexity of the treatment, handling, and storage of the waste. The DOE is the largest holder and generator of mixed waste. Its mixed wastes are classified as either high-level, transuranic (TRU), or low-level waste (LLW). High-level mixed wastes will be treated in vitrification plants. Transuranic wastes may be disposed of without treatment by obtaining a no-migration variance from the EPA. Lowlevel wastes, however, will require treatment, but treatment systems with sufficient capacity are not yet available to DOE. Various facilities are being proposed for the treatment of low-level waste. The concept described in this paper represents one option for establishing that treatment capacity

  2. Solid waste electron beam treatment

    International Nuclear Information System (INIS)

    Chmielewski, A.G.

    1998-01-01

    The possible applications of electron accelerators for solid waste treatment are discussed in the report. The elaborated technologies allow to recycle of materials (e.g. cellulosic materials in municipal waste), improve their hygienic standards (agricultural usage of sludge from municipal waste water treatment) and reduce harmful to environment chemical usage (cellulose degradation). These are environment friendly advanced technologies which meets demands waste recycling. (author)

  3. Solid waste electron beam treatment

    Energy Technology Data Exchange (ETDEWEB)

    Chmielewski, A G

    1998-07-01

    The possible applications of electron accelerators for solid waste treatment are discussed in the report. The elaborated technologies allow to recycle of materials (e.g., cellulosic materials in municipal waste), improve their hygienic standards (agricultural usage of sludge from municipal waste water treatment) and reduce harmful to environment chemical usage (cellulose degradation). These are environment friendly advanced technologies which meets demands waste recycling. (author)

  4. Thermal treatment for TRU waste sorting

    International Nuclear Information System (INIS)

    Sasaki, Toshiki; Aoyama, Yoshio; Yamashita, Toshiyuki

    2009-03-01

    A thermal treatment that can automatically unpack TRU waste and remove hazardous materials has been developed to reduce the risk of radiation exposure and save operation cost. The thermal treatment is a process of removing plastic wrapping and hazardous material from TRU waste by heating waste at 500 to 700degC. Plastic wrappings of simulated wastes were removed using a laboratory scale thermal treatment system. Celluloses and isoprene rubbers that must be removed from waste for disposal were pyrolyzed by the treatment. Although the thermal treatment can separate lead and aluminum from the waste, a further technical development is needed to separate lead and aluminum. A demonstration scale thermal treatment system that comprises a rotary kiln with a jacket water cooler and a rotating inner cage for lead and aluminum separation is discussed. A clogging prevention system against zinc chloride, a lead and aluminum accumulation system, and a detection system for spray cans that possibly cause explosion and fire are also discussed. Future technology development subjects for the TRU waste thermal treatment system are summarized. (author)

  5. Radiant-heat spray-calcination process for the solid fixation of radioactive waste. Part 1, Non-radioactive pilot unit

    Energy Technology Data Exchange (ETDEWEB)

    Allemann, R.T.; Johnson, B.M. Jr.

    1960-11-14

    The fixation of radioactive waste in a stable solid media by means of calcination of these aqueous solutions has been the subject of considerable-effort throughout the U. S. Atomic Energy Commission and by atomic energy organizations in other countries. Several methods of doing this on a continuous or semi-continuous basis have been devised, and a fev have been demonstrated to be feasible for the handling of non-radioactive, or low-activity, simulated wastes. Notable among methods currently under development are: (a) batch-operated pot calcination of waste generated from reprocessing stainless steel clad fuel elements (Darex process) and Purex waste, (b) combination rotary kiln and ball mill calcination of aluminum nitrate (TBP-25 and Redox process), and (c) fluidized bed calcination of TBP-25 and Purex wastes. Although a considerable amount of engineering experience has been obtained on the calcination of dissolved salts in a fluidized bed, and the other methods have been the subjects of a great deal of study, none of them have been developed to-the extent which would rule out the desirability of further investigation of other possible methods of calcination.

  6. Tank waste treatment science

    International Nuclear Information System (INIS)

    LaFemina, J.P.; Blanchard, D.L.; Bunker, B.C.; Colton, N.G.; Felmy, A.R.; Franz, J.A.; Liu, J.; Virden, J.W.

    1994-01-01

    Remediation efforts at the U.S. Department of Energy's Hanford Site require that many technical and scientific principles be combined for effectively managing and disposing the variety of wastes currently stored in underground tanks. Based on these principles, pretreatment technologies are being studied and developed to separate waste components and enable the most suitable treatment methods to be selected for final disposal of these wastes. The Tank Waste Treatment Science Task at Pacific Northwest Laboratory is addressing pretreatment technology development by investigating several aspects related to understanding and processing the tank contents. The experimental work includes evaluating the chemical and physical properties of the alkaline wastes, modeling sludge dissolution, and evaluating and designing ion exchange materials. This paper gives some examples of results of this work and shows how these results fit into the overall Hanford waste remediation activities. This work is part of series of projects being conducted for the Tank Waste Remediation System

  7. Hanford Tank Waste - Near Source Treatment of Low Activity Waste

    International Nuclear Information System (INIS)

    Ramsey, William Gene

    2013-01-01

    Abstract only. Treatment and disposition of Hanford Site waste as currently planned consists of 100+ waste retrievals, waste delivery through up to 8+ miles of dedicated, in-ground piping, centralized mixing and blending operations- all leading to pre-treatment combination and separation processes followed by vitrification at the Hanford Tank Waste Treatment and Immobilization Plant (WTP). The sequential nature of Tank Farm and WTP operations requires nominally 15-20 years of continuous operations before all waste can be retrieved from many Single Shell Tanks (SSTs). Also, the infrastructure necessary to mobilize and deliver the waste requires significant investment beyond that required for the WTP. Treating waste as closely as possible to individual tanks or groups- as allowed by the waste characteristics- is being investigated to determine the potential to 1) defer, reduce, and/or eliminate infrastructure requirements, and 2) significantly mitigate project risk by reducing the potential and impact of single point failures. The inventory of Hanford waste slated for processing and disposition as LAW is currently managed as high-level waste (HLW), i.e., the separation of fission products and other radionuclides has not commenced. A significant inventory of this waste (over 20M gallons) is in the form of precipitated saltcake maintained in single shell tanks, many of which are identified as potential leaking tanks. Retrieval and transport (as a liquid) must be staged within the waste feed delivery capability established by site infrastructure and WTP. Near Source treatment, if employed, would provide for the separation and stabilization processing necessary for waste located in remote farms (wherein most of the leaking tanks reside) significantly earlier than currently projected. Near Source treatment is intended to address the currently accepted site risk and also provides means to mitigate future issues likely to be faced over the coming decades. This paper

  8. The subject-fixated coaxially sighted corneal light reflex: a clinical marker for centration of refractive treatments and devices.

    Science.gov (United States)

    Chang, Daniel H; Waring, George O

    2014-11-01

    To describe the inconsistencies in definition, application, and usage of the ocular reference axes (optical axis, visual axis, line of sight, pupillary axis, and topographic axis) and angles (angle kappa, lambda, and alpha) and to propose a precise, reproducible, clinically defined reference marker and axis for centration of refractive treatments and devices. Perspective. Literature review of papers dealing with ocular reference axes, angles, and centration. The inconsistent definitions and usage of the current ocular axes, as derived from eye models, limit their clinical utility. With a clear understanding of Purkinje images and a defined alignment of the observer, light source/fixation target, and subject eye, the subject-fixated coaxially sighted corneal light reflex can be a clinically useful reference marker. The axis formed by connecting the subject-fixated coaxially sighted corneal light reflex and the fixation point, the subject-fixated coaxially sighted corneal light reflex axis, is independent of pupillary dilation and phakic status of the eye. The relationship of the subject-fixated coaxially sighted corneal light reflex axis to a refined definition of the visual axis without reference to nodal points, the foveal-fixation axis, is discussed. The displacement between the subject-fixated coaxially sighted corneal light reflex and pupil center is described not by an angle, but by a chord, here termed chord mu. The application of the subject-fixated coaxially sighted corneal light reflex to the surgical centration of refractive treatments and devices is discussed. As a clinically defined reference marker, the subject-fixated coaxially sighted corneal light reflex avoids the shortcomings of current ocular axes for clinical application and may contribute to better consensus in the literature and improved patient outcomes. Copyright © 2014 Elsevier Inc. All rights reserved.

  9. Hybrid external fixation in the treatment of tibial pilon fractures: A retrospective analysis of 162 fractures.

    Science.gov (United States)

    Galante, Vito N; Vicenti, Giovanni; Corina, Gianfranco; Mori, Claudio; Abate, Antonella; Picca, Girolamo; Conserva, Vito; Speciale, Domenico; Scialpi, Lorenzo; Tartaglia, Nicola; Caiaffa, Vincenzo; Moretti, Biagio

    2016-10-01

    To determine the efficacy of hybrid external fixation in the treatment of tibial pilon fractures. Retrospective, multicentre study. Adult patients with tibial pilon fractures treated with hybrid external fixation. Fracture reduction with ligamentotaxis and fixation with XCaliber hybrid external fixator. Fracture union, complications, functional outcome (Mazur Ankle Score). Union was obtained in 159 fractures at an average of 125days; there were three delayed unions and three non-unions. The most frequent complication was superficial pin-track infections (48), all of which responded to local wound care and antibiotics. There were no deep infections and no DVT. Only one fracture had loss of reduction that required frame revision. The overall functional scores were 91 (excellent) for AO/OTA type A fractures, 89 (good) for type B fractures, and 75 (satisfactory) for type C fractures. Hybrid external fixation is an effective method of stabilising tibial pilon fractures, particularly those with marked comminution. The minimally-invasive technique and stable fixation enable early mobilisation, with good functional results and minimal complications. Level IV Case series. Copyright © 2016 Elsevier Ltd. All rights reserved.

  10. In situ chemical fixation of arsenic-contaminated soils: Anexperimental study

    Energy Technology Data Exchange (ETDEWEB)

    Yang, Li; Donahoe, Rona J.; Redwine, James C.

    2007-03-27

    This paper reports the results of an experimentalstudytesting a low-cost in situ chemical fixation method designed to reclaimarsenic-contaminated subsurface soils. Subsurface soils from severalindustrial sites in southeastern U.S. were contaminated with arsenicthrough heavy application of herbicide containing arsenic trioxide. Themean concentrations of environmentally available arsenic in soilscollected from the two study sites, FW and BH, are 325 mg/kg and 900mg/kg, respectively. The soils are sandy loams with varying mineralogicaland organic contents. The previous study [Yang L, Donahoe RJ. The form,distribution and mobility of arsenic in soils contaminated by arsenictrioxide, at sites in Southeast USA. Appl Geochem 2007;22:320 341]indicated that a large portion of the arsenic in both soils is associatedwith amorphous aluminum and iron oxyhydroxides and shows very slowrelease against leaching by synthetic precipitation. The soil's amorphousaluminum and iron oxyhydroxides content was found to have the mostsignificant effect on its ability to retain arsenic.Based on thisobservation, contaminated soils were reacted with different treatmentsolutions in an effort to promote the formation of insolublearsenic-bearing phases and thereby decrease the leachability of arsenic.Ferrous sulfate, potassium permanganate and calcium carbonate were usedas the reagents for the chemical fixation solutions evaluated in threesets of batch experiments: (1) FeSO4; (2) FeSO4 and KMnO4; (3) FeSO4,KMnO4 and CaCO3. The optimum treatment solutions for each soil wereidentified based on the mobility of arsenic during sequential leaching oftreated and untreated soils using the fluids described in EPA Method 1311[USEPA. Method 1311: toxicity characteristic leaching procedure. Testmethods for evaluating solid waste, physical/chemical methods. 3rd ed.Washington, DC: U.S. Environmental Protection Agency, Office of SolidWaste. U.S. Government Printing Office; 1992]toxic characteristicsleaching

  11. Chemical engineering problems of radioactive waste fixation by vitrification

    International Nuclear Information System (INIS)

    Taylor, R.F.

    1985-01-01

    Basic features are reviewed of the chemical engineering problems faced in the vitrification of the high-level radioactive liquid wastes resulting from the reprocessing of nuclear fuel. After an outline of glass solution properties and formation kinetics the constituent elements of the vitrification route are examined in turn: waste feed evaporation and denitration, calcination, offgas treatment, and finally melting and product quality. Plant and experimental data for each stage are discussed with comparison between process routes and with reference to the underlying principles. Attention is drawn to the future need for higher trapping efficiencies and for dealing with a wider range of species in offgas treatments as higher burnup fuels are processed after shorter cooling times from reactor. Two areas of present study where deeper insight into underlying process mechanics is needed are, firstly, the association of waste material with glass formers in the wet or sinter stages and secondly their incorporation and mixing reaction in the melt. Fuller understanding here would bring direct benefit to process performance and handling. The problems discussed are not of a nature to jeopardize the vitrification routes but if product quality does come to rely heavily on process control then demonstrable confidence in the behaviour of the central physico-chemical interactions is indispensable. (author)

  12. Clinical comparative analysis on unstable pelvic fractures in the treatment with percutaneous sacroiliac screws and sacroiliac joint anterior plate fixation.

    Science.gov (United States)

    Li, C-L

    2014-01-01

    To investigate clinical efficacy of unstable pelvic fractures in the treatment with percutaneous sacroiliac screws and sacroiliac joint anterior plate fixation. 64 patients with unstable pelvic fractures were selected in the hospital from January 2008 to June 2011, and were randomly divided into two groups.(32 patients with sacroiliac anterior plate fixation as the control group, and another 32 patients with percutaneous sacroiliac screw internal fixation as the observation group). The perioperative period clinical indicators, postoperative Matta score, postoperative Majeed function score of all patients were compared and analyzed. The operation time, intraoperative blood loss, wound total length, postoperative fever time, duration of hospitalization in the observation group were significantly less than those in the control group. The complication rate (3.1%) in the observation group was lower than that in the control group (21.9%). The rate of Matta score excellent (96.9%) in the observation group was higher than that in the control group (81.2%) after the treatment. The rate of Majeed function score excellent (93.8%) in the observation group was significantly higher than that in the control group (75%) after the treatment. Percutaneous sacroiliac screw internal fixation in the treatment of unstable pelvic fractures has less injury, less bleeding, less pain and rapid recovery which is a safe and effective minimally invasive operation method. The clinical curative effect of percutaneous sacroiliac screw internal fixation is better than anterior plate fixation for the treatment of sacroiliac joint. The full preparation before the surgery and patients with positive can substantially reduce the occurrence of complications rate.

  13. Fixation process for radioactive waste

    International Nuclear Information System (INIS)

    Theysohn, F.

    1977-01-01

    An improvement on the method of solidification of radioactive liquid waste in bitumen with the aid of extruders is described. So far, it has been difficult to remove large amounts of water. The waste sludge, as proposed here, is pre-dried in the extruder and then mixed with the bitumen. The extruder is inclined upward in the transport direction, and its barrel extruders have through holes parallel to the direction of transport in the raised sides of the passages, so that water runs back. Also the waste steam nozzles are arranged before the bitumen inlet. (UWI) [de

  14. Mixed waste treatment model: Basis and analysis

    International Nuclear Information System (INIS)

    Palmer, B.A.

    1995-09-01

    The Department of Energy's Programmatic Environmental Impact Statement (PEIS) required treatment system capacities for risk and cost calculation. Los Alamos was tasked with providing these capacities to the PEIS team. This involved understanding the Department of Energy (DOE) Complex waste, making the necessary changes to correct for problems, categorizing the waste for treatment, and determining the treatment system requirements. The treatment system requirements depended on the incoming waste, which varied for each PEIS case. The treatment system requirements also depended on the type of treatment that was desired. Because different groups contributing to the PEIS needed specific types of results, we provided the treatment system requirements in a variety of forms. In total, some 40 data files were created for the TRU cases, and for the MLLW case, there were 105 separate data files. Each data file represents one treatment case consisting of the selected waste from various sites, a selected treatment system, and the reporting requirements for such a case. The treatment system requirements in their most basic form are the treatment process rates for unit operations in the desired treatment system, based on a 10-year working life and 20-year accumulation of the waste. These results were reported in cubic meters and for the MLLW case, in kilograms as well. The treatment system model consisted of unit operations that are linked together. Each unit operation's function depended on the input waste streams, waste matrix, and contaminants. Each unit operation outputs one or more waste streams whose matrix, contaminants, and volume/mass may have changed as a result of the treatment. These output streams are then routed to the appropriate unit operation for additional treatment until the output waste stream meets the treatment requirements for disposal. The total waste for each unit operation was calculated as well as the waste for each matrix treated by the unit

  15. A process for treatment of mixed waste containing chemical plating wastes

    International Nuclear Information System (INIS)

    Anast, K.R.; Dziewinski, J.; Lussiez, G.

    1995-01-01

    The Waste Treatment and Minimization Group at Los Alamos National Laboratory has designed and will be constructing a transportable treatment system to treat low-level radioactive mixed waste generated during plating operations. The chemical and plating waste treatment system is composed of two modules with six submodules, which can be trucked to user sites to treat a wide variety of aqueous waste solutions. The process is designed to remove the hazardous components from the waste stream, generating chemically benign, disposable liquids and solids with low level radioactivity. The chemical and plating waste treatment system is designed as a multifunctional process capable of treating several different types of wastes. At this time, the unit has been the designated treatment process for these wastes: Destruction of free cyanide and metal-cyanide complexes from spent plating solutions; destruction of ammonia in solution from spent plating solutions; reduction of Cr VI to Cr III from spent plating solutions, precipitation, solids separation, and immobilization; heavy metal precipitation from spent plating solutions, solids separation, and immobilization, and acid or base neutralization from unspecified solutions

  16. Treatment Approach for Infection of Healed Fractures After Internal Fixation.

    Science.gov (United States)

    Lawrenz, Joshua M; Frangiamore, Salvatore J; Rane, Ajinkya A; Cantrell, William Alex; Vallier, Heather A

    2017-11-01

    To review the efficacy of a treatment approach for patients with infection and colonized implants after open reduction and internal fixation of fractures. Retrospective case series. Level one trauma center. Twenty patients were treated for wound infection with colonized implants after open reduction and internal fixation. Surgical debridement, removal of implants, and a short postoperative oral antibiotic course. The course of patients after surgical debridement and removal of implants, including culture results, antibiotic administration, and presence of recurrent clinical infection and radiographic union. Twenty patients had clinical presentations, including skin breakdown, serous drainage, purulent drainage and/or exposed implants, most commonly of the tibia (15 of 20). Mean time from index procedure to debridement with implant removal was 19.7 months. At the time of debridement and implant removal, 18 of 20 (90%) patients had a positive intraoperative culture (16 routine cultures and 2 broth cultures). The most common bacteria were Enterobacter cloacae (5/17) and methicillin-sensitive Staphylococcus aureus (4/17). All patients had soft tissue healing without signs of recurrent infection after mean follow up of 40 months after implant removal. Surgical debridement with implant removal plus a short oral antibiotic course is effective to resolve wound infection with a colonized implant in the setting of healed fracture after internal fixation. Therapeutic Level IV. See Instructions for Authors for a complete description of levels of evidence.

  17. SR and LR Union Suture for the Treatment of Myopic Strabismus Fixus: Is Scleral Fixation Necessary?

    Directory of Open Access Journals (Sweden)

    Carol P. S. Lam

    2015-01-01

    Full Text Available Purpose. To evaluate and compare the effectiveness of scleral fixation SR and LR union suture and nonscleral fixation union suture for the treatment of myopic strabismus fixus. Methods. Retrospective review of 32 eyes of 22 patients with myopic strabismus fixus who had undergone union suture of superior rectus (SR and lateral rectus (LR with or without scleral fixation, and follow-up longer than 6 months at Hong Kong Eye Hospital from 2006 to 2013. Surgical techniques and outcomes in terms of ocular alignment are analyzed. Results. There is significant overall improvement both in postoperative angle of esodeviation (P0.05. Conclusions. Union suture of SR and LR is an effective procedure in correcting myopic strabismus fixus. Fixation of the union suture to the sclera does not improve surgical outcome.

  18. Waste management system alternatives for treatment of wastes from spent fuel reprocessing

    International Nuclear Information System (INIS)

    McKee, R.W.; Swanson, J.L.; Daling, P.M.

    1986-09-01

    This study was performed to help identify a preferred TRU waste treatment alternative for reprocessing wastes with respect to waste form performance in a geologic repository, near-term waste management system risks, and minimum waste management system costs. The results were intended for use in developing TRU waste acceptance requirements that may be needed to meet regulatory requirements for disposal of TRU wastes in a geologic repository. The waste management system components included in this analysis are waste treatment and packaging, transportation, and disposal. The major features of the TRU waste treatment alternatives examined here include: (1) packaging (as-produced) without treatment (PWOT); (2) compaction of hulls and other compactable wastes; (3) incineration of combustibles with cementation of the ash plus compaction of hulls and filters; (4) melting of hulls and failed equipment plus incineration of combustibles with vitrification of the ash along with the HLW; (5a) decontamination of hulls and failed equipment to produce LLW plus incineration and incorporation of ash and other inert wastes into HLW glass; and (5b) variation of this fifth treatment alternative in which the incineration ash is incorporated into a separate TRU waste glass. The six alternative processing system concepts provide progressively increasing levels of TRU waste consolidation and TRU waste form integrity. Vitrification of HLW and intermediate-level liquid wastes (ILLW) was assumed in all cases

  19. A Primer on Waste Water Treatment.

    Science.gov (United States)

    Department of the Interior, Washington, DC. Federal Water Pollution Control Administration.

    This information pamphlet is for teachers, students, or the general public concerned with the types of waste water treatment systems, the need for further treatment, and advanced methods of treating wastes. Present day pollution control methods utilizing primary and secondary waste treatment plants, lagoons, and septic tanks are described,…

  20. Hazardous waste treatment facility and skid-mounted treatment systems at Los Alamos

    International Nuclear Information System (INIS)

    Lussiez, G.W.; Zygmunt, S.J.

    1993-01-01

    To centralize treatment, storage, and staging areas for hazardous wastes, Los Alamos National Laboratory has designed a 12,000-ft 2 hazardous waste treatment facility. The facility will house a treatment room for each of four kinds of wastes: nonradioactive characteristic wastes, nonradioactive listed wastes radioactive characteristic wastes, and radioactive listed wastes. The facility will be used for repacking labpacks, bulking small organic waste volumes, processing scintillation vials, treating reactives such as lithium hydride and pyrophoric uranium, treating contaminated solids such as barium sand, and treating plating wastes. The treated wastes will then be appropriately disposed of. This report describes the integral features of the hazardous waste treatment facility

  1. Sustainable treatment of municipal waste water

    DEFF Research Database (Denmark)

    Hansen, Peter Augusto; Larsen, Henrik Fred

    The main goal of the EU FP6 NEPTUNE program is to develop new and improve existing waste water treatment technologies (WWTT) and sludge handling technologies for municipal waste water, in accordance with the concepts behind the EU Water Framework Directive. As part of this work, the project.......e. heavy metals, pharmaceuticals and endocrine disruptors) in the waste water. As a novel approach, the potential ecotoxicity and human toxicity impacts from a high number of micropollutants and the potential impacts from pathogens will be included. In total, more that 20 different waste water and sludge...... treatment technologies are to be assessed. This paper will present the first LCA results from running existing life cycle impact assessment (LCIA) methodology on some of the waste water treatment technologies. Keywords: Sustainability, LCA, micropollutants, waste water treatment technologies....

  2. Chemical aspects of nuclear waste treatment

    International Nuclear Information System (INIS)

    Bond, W.D.

    1980-01-01

    The chemical aspects of the treatment of gaseous, liquid, and solid wastes are discussed in overview. The role of chemistry and the chemical reactions in waste treatment are emphasized. Waste treatment methods encompass the chemistry of radioactive elements from every group of the periodic table. In most streams, the radioactive elements are present in relatively low concentrations and are often associated with moderately large amounts of process reagents, or materials. In general, it is desirable that waste treatment methods are based on chemistry that is selective for the concentration of radionuclides and does not require the addition of reagents that contribute significantly to the volume of the treated waste. Solvent extraction, ion exchange, and sorbent chemistry play a major role in waste treatment because of the high selectivity provided for many radionuclides. This paper deals with the chemistry of the onsite treatment methods that is typically used at nuclear installations and is not concerned with the chemistry of the various alternative materials proposed for long-term storage of nuclear wastes. The chemical aspects are discussed from a generic point of view in which the chemistry of important radionuclides is emphasized

  3. Treatment of Early Post-Op Wound Infection after Internal Fixation

    Science.gov (United States)

    2016-10-01

    Obremskey, M.D. CONTRACTING ORGANIZATION: Vanderbilt University Medical Center Nashville TN 37203 REPORT DATE: October 2016 TYPE OF REPORT: Annual...NOT RETURN YOUR FORM TO THE ABOVE ADDRESS. 1. REPORT DATE (DD-MM-YYYY) October 2016 2. REPORT TYPE Annual 3. DATES COVERED (From - To) 15Sep2015...effect of treatment of post-op wound infection in long bones after fracture fixation or joint fusion and either: (Group 1) operative debridement and

  4. Final treatment of liquid radioactive wastes

    International Nuclear Information System (INIS)

    Svolik, S.

    2004-01-01

    Final treatment of liquid radioactive wastes which are produced by 1 st and 2 nd bloc of the Mochovce NPP, prepares the NPP in its natural range. The purpose of the equipment is liquidation of wastes, which are formed at production. Wastes are warehoused in the building of active auxiliary plants in the present time, where are reservoirs in which they are deposited. Because they are already feeling and in 2006 year they should be filled definitely, it is necessary to treat them in that manner, so as they may be liquidated. Therefore the Board of directors of the Slovenske elektrarne has disposed about construction of final treatment of liquid radioactive wastes in the Mochovce NPP. Because of transport the wastes have to be treated in the locality of power plant. Technically, the final treatment of the wastes will be interconnected with building of active operation by bridges. These bridges will transport the wastes for treatment into processing centre

  5. Treatment of inherently unstable open or infected fractures by open wound management and external skeletal fixation.

    Science.gov (United States)

    Ness, M G

    2006-02-01

    To assess the use of external skeletal fixation with open wound management for the treatment of inherently unstable open or infected fractures in dogs. A retrospective review of 10 cases. Fracture stabilisation and wound management required only a single anaesthetic, and despite the challenging nature of these injuries, the final outcome was acceptable or good in every case. However, minor complications associated with the fixator pins were quite common, and two dogs developed complications which required additional surgery. Open management of wounds, even when bone was exposed, proved to be an effective technique, and external skeletal fixators were usually effective at maintaining stability throughout an inevitably extended fracture healing period.

  6. Fixation stability and implication for multifocal electroretinography in patients with neovascular age-related macular degeneration after anti-VEGF treatment

    DEFF Research Database (Denmark)

    Pedersen, Karen Bjerg; Sjølie, Anne Katrin; Vestergaard, Anders Højslet

    2016-01-01

    Purpose: To quantify fixation stability in patients with neovascular age-related macular degeneration (nAMD) at baseline, 3 and 6 months after anti-vascular endothelial growth factor (anti-VEGF) treatment and furthermore asses the implications of an unsteady fixation for multifocal...

  7. Treatment of radioactive wastes

    International Nuclear Information System (INIS)

    Machida, Chuji

    1976-01-01

    Japan Atomic Energy Research Institute (JAERI) is equipped with such atomic energy facilities as a power test reactor, four research reactors, a hot laboratory, and radioisotope-producing factory. All the radioactive wastes but gas generated from these facilities are treated by the waste treatment facilities established in JAERI. The wastes carried into JAERI through Japan Radioisotope Association are also treated there. Low level water solution is treated with an evaporating apparatus, an ion-exchange apparatus, and a cohesive precipitating apparatus, while medium level solution is treated with an evaporating apparatus, and low level combustible solid is treated with an incinerating apparatus. These treated wastes and sludges are mixed with Portland cement in drum cans to solidify, and stored in a concrete pit. The correct classification and its indication as well as the proper packing for the wastes are earnestly demanded by the treatment facilities. (Kobatake, H.)

  8. Technologies 1995: environment and wastes treatment

    International Nuclear Information System (INIS)

    Anon.

    1995-03-01

    From new technical or scientific developments, new products launching, and markets evolutions, this catalog gives informations selection on research and development projects, new fabrication processes, activities and plants strategies, licences or technology transfers opportunities. The covered fields are: atmospheric pollution controls, water and liquid wastes treatment, polluted soils treatments, noise and odors treatments, municipal and industrial wastes treatments (metal, plastic, paper, glass), clean materials and technologies, radioactive wastes, and european cooperation programs. (A.B.)

  9. Enhancement of Apoptosis by Titanium Alloy Internal Fixations during Microwave Treatments for Fractures: An Animal Study.

    Directory of Open Access Journals (Sweden)

    Gang Wang

    Full Text Available Microwaves are used in one method of physical therapy and can increase muscle tissue temperature which is useful for improving muscle, tendon and bone injuries. In the study, we sought to determine whether titanium alloy internal fixations influence apoptosis in tissues subjected to microwave treatments at 2,450 MHz and 40 W during the healing of fractures because this issue is not yet fully understood.In this study, titanium alloy internal fixations were used to treat 3.0-mm transverse osteotomies in the middle of New Zealand rabbits' femurs. After the operation, 30-day microwave treatments were applied to the 3.0 mm transverse osteotomies 3 days after the operation. The changes in the temperatures of the muscle tissues in front of the implants or the 3.0 mm transverse osteotomies were measured during the microwave treatments. To characterize the effects of titanium alloy internal fixations on apoptosis in the muscles after microwave treatment, we performed TUNEL assays, fluorescent real-time (quantitative PCR, western blotting analyses, reactive oxygen species (ROS detection and transmission electron microscopy examinations.The temperatures were markedly increased in the animals with the titanium alloy implants. Apoptosis in the muscle cells of the implanted group was significantly more extensive than that in the non-implanted control group at different time points. Transmission electron microscopy examinations of the skeletal muscles of the implanted groups revealed muscular mitochondrial swelling, vacuolization. ROS, Bax and Hsp70 were up-regulated, and Bcl-2 was down-regulated in the implanted group.Our results suggest that titanium alloy internal fixations caused greater muscular tissue cell apoptosis following 2,450 MHz, 40 W microwave treatments in this rabbit femur fracture models.

  10. [Long-term efficacy of open reduction and internal fixation versus external fixation for unstable distal radius fractures: a meta-analysis].

    Science.gov (United States)

    Yang, Z; Yuan, Z Z; Ma, J X; Ma, X L

    2017-11-07

    Objective: To make a systematic assessment of the Long-term efficacy of open reduction and internal fixation versus external fixation for unstable distal radius fractures. Methods: A computer-based online search of PubMed, ScienceDirect, EMBASE, BIOSIS, Springer and Cochrane Library were performed. The randomized and controlled trials of open reduction and internal fixation versus external fixation for unstable distal radius fractures were collected. The included trials were screened out strictly based on the criterion of inclusion and exclusion. The quality of included trials was evaluated. RevMan 5.0 was used for data analysis. Results: Sixteen studies involving 1 268 patients were included. There were 618 patients with open reduction and internal fixation and 650 with external fixation. The results of meta-analysis indicated that there were statistically significant differences with regard to the complications postoperatively (infection( I (2)=0%, RR =0.27, 95% CI 0.16-0.45, Z =4.92, P internal fixation and external fixation are effective treatment for unstable distal radius fractures. Compared with external fixation, open reduction and internal fixation provides reduced complications postoperatively, lower DASH scores and better restoration of volar tilt for treatment of distal radius fractures.

  11. Transpedicular fixation for the espondilolistesis treatment, espondilolisis and channel lumbar narrow of the lumbosacral column

    International Nuclear Information System (INIS)

    Matta Javier Ernesto; Diaz, Cesar Jacobo; Gamba S, Cesar Enrique

    2002-01-01

    A descriptive, prospective study was designs with the objective of analyzing the experience with the technique of transpedicular fixation, for the treatment of degenerative espondilolistesis, espondilolisis and channel lumbar narrow. Eighty patients (42 men and 38 women) they were intervened between February of 1992 and February of 2002; the age average was of 46,3 years and the minimum pursuit of 7 months. The cases were tabulated according to the diagnostic, clinical presentation, previous interventions, descompressive procedures associated to the fixation, anatomical level of lesion, number of fixed vertebras, number of placed screws, type of bony implants and complications. In 33 patients (41,3%) it diagnose degenerative espondilolistesis, espondilolisis in 24 (30%), channel lumbar narrow in 20 (25%), displasic espondilolistesis in 2,5% and espondiloptosis in 1%. the clinical presentations more frequent were radicular and lumbar pain, with 33,8 each one; one carries out arthrodesis 15-S1 in 38 patients (47,5%) and 14 15 in 15 patients (18,7%). as complications we find deep infection in 7,5% of the cases, neurological deficit in 5%, rupture of duramadre 3,8%, false route of screws, bony failure and material rupture in 2,5% each one and seroma in 1,3%. Doesn't present seudoarthrosis. The transpedicular fixation is a sure technique for the treatment of the degenerative espondilolistesis, espondilolisis and channel lumbar narrow. With the transpedicular fixation the average of fixed vertebras is smaller than with the Harrington and Luque techniques, preserving in more degree the mobility to articulate. The association of the transpedicular fixation with arthrodesis and coalition by means of placement of autogenous implants diminishes the seudoarthrosis incidence

  12. Fugitive dust control experiments using soil fixatives on vehicle traffic surfaces

    International Nuclear Information System (INIS)

    Winberg, M.R.; Wixom, V.E.

    1992-08-01

    This report presents the results of engineering scale dust control experiments using soil fixative for contamination control during handling of transuranic waste. These experiments focused on controlling dust during retrieval operations of buried waste where waste and soil are intimately mixed. Sources of dust generation during retrieval operations include digging, dumping, and vehicle traffic. Because contaminants are expected to attach to soil particles and move with the generated dust, control of the dust spread may be the key to contamination control. Dust control techniques examined in these experiments include the use of soil fixatives to control generation of fugitive dusts during vehicle traffic operations. Previous experiments conducted in FY 1990 included testing of the soil fixative, ENTAC. These experiments showed that ENTAC was effective in controlling dust generation but had several undesirable properties such as slow cure times and clogged the pumps and application nozzles. Therefore, other products would have to be evaluated to find a suitable candidate. As a result, two soil fixatives were tested in these present experiments, COHEREX-PM, an asphalt emulsion product manufactured by Witco Corporation and FLAMBINDER, a calcium lignosulfonate product manufactured by Flambeau Corporation. The results of the experiments include product performance and recommended application methods for application in a field deployable contamination control unit to be built in FY 1993

  13. Treatment of nanomaterial-containing waste in thermal waste treatment facilities; Behandlung nanomaterialhaltiger Abfaelle in thermischen Abfallbehandlungsanlagen

    Energy Technology Data Exchange (ETDEWEB)

    Vogel, Julia; Weiss, Volker [Umweltbundesamt, Dessau-Rosslau (Germany); Oischinger, Juergen; Meiller, Martin; Daschner, Robert [Fraunhofer Umsicht, Sulzbach-Rosenberg (Germany)

    2016-09-15

    There is already a multitude of products on the market, which contain synthetic nanomaterials (NM), and for the coming years an increase of such products can be expected. Consequently, it is predictable that more nanomaterial-containing waste will occur in the residual waste that is predominately disposed in thermal waste treatment plants. However, the knowledge about the behaviour and effects of nanomaterials from nanomaterial-containing waste in this disposal route is currently still low. A research project of the German Environment Agency on the ''Investigation of potential environmental impacts when disposing nanomaterial-containing waste in waste treatment plants'' will therefore dedicate itself to a detailed examination of emission pathways in the thermal waste treatment facilities. The tests carried out i.a. on an industrial waste incineration plant and a sludge incineration plant with controlled addition of titanium dioxide at the nanoscale, showed that no increase in the emissions of NM in the exhaust gas was detected. The majority of the NM was found in the combustion residues, particularly the slag.

  14. Temporary Stabilization with External Fixator in 'Tripolar' Configuration in Two Steps Treatment of Tibial Pilon Fractures.

    Science.gov (United States)

    Daghino, Walter; Messina, Marco; Filipponi, Marco; Alessandro, Massè

    2016-01-01

    The tibial pilon fractures represent a complex therapeutic problem for the orthopedic surgeon, given the frequent complications and outcomes disabling. The recent medical literature indicates that the best strategy to reduce amount of complications in tibial pilon fractures is two-stages procedure. We describe our experience in the primary stabilization of these fractures. We treated 36 cases with temporary external fixation in a simple configuration, called "tripolar": this is an essential structure (only three screws and three rods), that is possible to perform even without the availability of X-rays and with simple anesthesia or sedation. We found a sufficient mechanical stability for the nursing post-operative, in absence of intraoperative and postoperative problems. The time between trauma and temporary stabilization ranged between 3 and 144 hours; surgical average time was 8.4 minutes. Definitive treatment was carried out with a delay of a minimum of 4 and a maximum of 15 days from the temporary stabilization, always without problems, both in case of ORIF (open reduction, internal fixation) or circular external fixation. Temporary stabilization with external fixator in 'tripolar' configuration seems to be the most effective strategy in two steps treatment of tibial pilon fractures. These preliminary encouraging results must be confirmed by further studies with more cases.

  15. Development of radioactive waste treatment technique

    International Nuclear Information System (INIS)

    Kikuchi, Makoto; Amamiya, Shigeru; Yusa, Hideo.

    1984-01-01

    The techniques of radioactive waste treatment are generally reviewed, placing emphasis on volume reduction and solidification techniques. After a brief description on the general process of radioactive waste treatment, some special technologies being developed by Hitachi Ltd. are explained. From the viewpoints of the volume reduction, long term management and final disposal of wastes, the pelletization of dried waste and the solidification with inorganic substances are considered. One of the features of the pelletization system is to treat various kinds of wastes such as concentrated liquid wastes and used resins by the same system. The flow diagram of the system and its special features are shown. The volume reduction achieved by this system as compared to the conventional method is about 1/7. The first commercial plant for the treatment of concentrated liquid waste is scheduled to begin operation in June, 1984. As for the solidification technique for waste disposal, the use of cement glass is considered. The solidification system being developed is shortly described. (Aoki, K.)

  16. [Clinical application of atlas translaminar screws fixation in treatment of atlatoaxial instability].

    Science.gov (United States)

    Wang, Guoyou; Fu, Shijie; Shen, Huarui; Guan, Taiyuan; Xu, Ping

    2013-10-01

    To explore the effectiveness of fixation of atlas translaminar screws in the treatment of atlatoaxial instability. A retrospective analysis was made on the clinical data of 32 patients with atlatoaxial instability treated with atlantoaxial trans-pedicle screws between March 2007 and August 2009. Of them, 7 patients underwent atlas translaminar screws combined with axis transpedicle screws fixation because of fracture types, anatomic variation, and intraoperative reason, including 5 males and 2 females with an average age of 48.2 years (range, 35-69 years). A total of 9 translaminar screws were inserted. Injury was caused by traffic accident in 4 cases, falling from height in 2 cases, and crushing in 1 case. Two cases had simple odontoid fracture (Anderson type II), and 5 cases had odontoid fracture combined with other injuries (massa lateralis atlantis fracture in 2, atlantoaxial dislocation in 1, and Hangman fracture in 2). The interval between injury and operation was 4-9 days (mean, 6 days). The preoperative Japanese Orthopaedic Association (JOA) score was 8.29 +/- 1.60. The X-ray films showed good position of the screws. Healing of incision by first intention was obtained, and no patient had injuries of the spinal cord injury, nerve root, and vertebral artery. Seven cases were followed up 9-26 months (mean, 14 months). Good bone fusion was observed at 8 months on average (range, 6-11 months). No loosening, displacement, and breakage of internal fixation, re-dislocation and instability of atlantoaxial joint, or penetrating of pedicle screw into the spinal canal and the spinal cord occurred. The JOA score was significantly improved to 15.29 +/- 1.38 at 6 months after operation (t = 32.078, P = 0.000). Atlas translaminar screws fixation has the advantages of firm fixation, simple operating techniques, and relative safety, so it may be a remedial measure of atlatoaxial instability.

  17. Liquid Radioactive Wastes Treatment: A Review

    Directory of Open Access Journals (Sweden)

    Yung-Tse Hung

    2011-05-01

    Full Text Available Radioactive wastes are generated during nuclear fuel cycle operation, production and application of radioisotope in medicine, industry, research, and agriculture, and as a byproduct of natural resource exploitation, which includes mining and processing of ores, combustion of fossil fuels, or production of natural gas and oil. To ensure the protection of human health and the environment from the hazard of these wastes, a planned integrated radioactive waste management practice should be applied. This work is directed to review recent published researches that are concerned with testing and application of different treatment options as a part of the integrated radioactive waste management practice. The main aim from this work is to highlight the scientific community interest in important problems that affect different treatment processes. This review is divided into the following sections: advances in conventional treatment of aqueous radioactive wastes, advances in conventional treatment of organic liquid wastes, and emerged technological options.

  18. Waste washing pre-treatment of municipal and special waste.

    Science.gov (United States)

    Cossu, Raffaello; Lai, Tiziana; Pivnenko, Kostyantyn

    2012-03-15

    Long-term pollution potential in landfills is mainly related to the quality of leachate. Waste can be conveniently treated prior to landfilling with an aim to minimizing future emissions. Washing of waste represents a feasible pre-treatment method focused on controlling the leachable fraction of residues and relevant impact. In this study, non-recyclable plastics originating from source segregation, mechanical-biological treated municipal solid waste (MSW), bottom ash from MSW incineration and automotive shredder residues (ASR) were treated and the removal efficiency of washing pre-treatment prior to landfilling was evaluated. Column tests were performed to simulate the behaviour of waste in landfill under aerobic and anaerobic conditions. The findings obtained revealed how waste washing treatment (WWT) allowed the leachability of contaminants from waste to be reduced. Removal rates exceeding 65% were obtained for dissolved organic carbon (DOC), chemical oxygen demand (COD) and Total Kjeldahl Nitrogen (TKN). A percentage decrease of approximately 60% was reached for the leachable fraction of chlorides, sulphates, fluoride and metals, as proved by a reduction in electric conductivity values (70%). Copyright © 2011 Elsevier B.V. All rights reserved.

  19. [Comparison study on locking compress plate external fixator and standard external fixator for treatment of tibial open fractures].

    Science.gov (United States)

    Wu, Gang; Luo, Xiaozhong; Tan, Lun; Lin, Xu; Wu, Chao; Guo, Yong; Zhong, Zewei

    2013-11-01

    To compare the clinical results of locking compress plate (LCP) as an external fixator and standard external fixator for treatment of tibial open fractures. Between May 2009 and June 2012, 59 patients with tibial open fractures were treated with LCP as an external fixator in 36 patients (group A), and with standard external fixator in 23 patients (group B). There was no significant difference in gender, age, cause of injury, affected side, type of fracture, location, and interval between injury and surgery between 2 groups (P > 0.05). The time of fracture healing and incision healing, the time of partial weight-bearing, the range of motion (ROM) of knee and ankle, and complications were compared between 2 groups. The incidence of pin-track infection in group A (0) was significantly lower than that in group B (21.7%) (P=0.007). No significant difference was found in the incidence of superficial infection and deep infection of incision, and the time of incision healing between 2 groups (P > 0.05). Deep vein thrombosis occurred in 5 cases of group A and 2 cases of group B, showing no significant difference (Chi(2)=0.036, P=0.085). All patients were followed up 15.2 months on average (range, 9-28 months) in group A, and 18.6 months on average (range, 9-47 months) in group B. The malunion rate and nonunion rate showed no significant difference between groups A and B (0 versus 13.0% and 0 versus 8.7%, P > 0.05); the delayed union rate of group A (2.8%) was significantly lower than that of group B (21.7%) (Chi(2)=5.573, P=0.018). Group A had shorter time of fracture healing, quicker partial weight-bearing, greater ROM of the knee and ankle than group B (P fracture, and has good patients' compliance, so it is helpful to do functional exercise, improve fracture healing and function recovery, and reduce the complication incidence.

  20. Solid waste treatment processes for space station

    Science.gov (United States)

    Marrero, T. R.

    1983-01-01

    The purpose of this study was to evaluate the state-of-the-art of solid waste(s) treatment processes applicable to a Space Station. From the review of available information a source term model for solid wastes was determined. An overall system is proposed to treat solid wastes under constraints of zero-gravity and zero-leakage. This study contains discussion of more promising potential treatment processes, including supercritical water oxidation, wet air (oxygen) oxidation, and chemical oxidation. A low pressure, batch-type treament process is recommended. Processes needed for pretreatment and post-treatment are hardware already developed for space operations. The overall solid waste management system should minimize transfer of wastes from their collection point to treatment vessel.

  1. Chemical treatment of mixed waste at the FEMP

    International Nuclear Information System (INIS)

    Honigford, L.; Sattler, J.; Dilday, D.; Cook, D.

    1996-01-01

    The Chemical Treatment Project is one in a series of projects implemented by the Fernald Environmental Management Project (FEMP) to treat mixed waste. The projects were initiated to address concerns regarding treatment capacity for mixed waste and to comply with requirements established by the Federal Facility Compliance Act. The Chemical Treatment Project is designed to utilize commercially available mobile technologies to perform treatment at the FEMP site. The waste in the Project consists of a variety of waste types with a wide range of hazards and physical characteristics. The treatment processes to be established for the waste types will be developed by a systematic approach including waste streams evaluation, projectization of the waste streams, and categorization of the stream. This information is utilized to determine the proper train of treatment which will be required to lead the waste to its final destination (i.e., disposal). This approach allows flexibility to manage a wide variety of waste in a cheaper, faster manner than designing a single treatment technology diverse enough to manage all the waste streams

  2. Waste minimization promotes biophysical treatment of complex petrochemical wastes in Israel

    Energy Technology Data Exchange (ETDEWEB)

    Lebel, A [Invirotreat International Ltd., Fulleron, CA (United States); Raveh, A [Raveh Ecology Ltd., Haifa (Israel)

    1994-12-31

    This work describes a full-scale waste treatment system which was put into operation in a petrochemical manufacturing plant in Israel for the purpose of detoxifying its complex organic waste stream. The treatment plant design incorporates an innovative waste management approach to accommodate the limited space allocated for the facility. Initial performance data indicate a high efficient inorganic waste reduction. 4 refs., 6 figs., 2 tabs.

  3. Waste minimization promotes biophysical treatment of complex petrochemical wastes in Israel

    Energy Technology Data Exchange (ETDEWEB)

    Lebel, A. [Invirotreat International Ltd., Fulleron, CA (United States); Raveh, A. [Raveh Ecology Ltd., Haifa (Israel)

    1993-12-31

    This work describes a full-scale waste treatment system which was put into operation in a petrochemical manufacturing plant in Israel for the purpose of detoxifying its complex organic waste stream. The treatment plant design incorporates an innovative waste management approach to accommodate the limited space allocated for the facility. Initial performance data indicate a high efficient inorganic waste reduction. 4 refs., 6 figs., 2 tabs.

  4. Incorporation of Savannah River Plant radioactive waste into concrete

    International Nuclear Information System (INIS)

    Stone, J.A.

    1975-01-01

    Results are reported of a laboratory-scale experimental program at the Savannah River Laboratory to gain information on the fixation of high-level radioactive wastes in concrete. Two concrete formulations, a High-Alumina Cement and a Portland Pozzalanic cement, were selected on the bases of leachability and compressive strength for the fixation of non-radioactive simulated wastes. Therefore, these two cements were selected for current studies for the fixation of actual Savannah River Plant high-level wastes. (U.S.)

  5. Intermaxillary Fixation Screw Morbidity in Treatment of Mandibular Fractures

    DEFF Research Database (Denmark)

    Florescu, Vlad-Andrei; Kofod, Thomas; Pinholt, Else Marie

    2016-01-01

    Purpose The aim of the present retrospective study was to investigate the morbidity of screws used for intermaxillary fixation (IMF) in the treatment of mandibular fractures. A review of the published data was also performed for a comparison of outcomes. Our hypothesis was that the use of screws...... for IMF of mandibular fractures would result in minimal morbidity. Materials and Methods Patients treated for mandibular fractures from 2007 to 2013, using screws for IMF, using the international diagnosis code for mandibular fracture, DS026, were anonymously selected (Department of Oral and Maxillofacial...... Surgery, Rigshospitalet, University Hospital of Copenhagen, Copenhagen, Denmark). The fracture type, radiographic findings, treatment modality, screw type and number, and root damage were recorded. For the outcome comparison, a review of the published data regarding iatrogenic dental root damage caused...

  6. Sulfur Fixation by Chemically Modified Red Mud Samples Containing Inorganic Additives: A Parametric Study

    Directory of Open Access Journals (Sweden)

    Yang Liu

    2016-01-01

    Full Text Available Sulfur retention ability of Bayer red mud from alumina plant was investigated. Bayer red mud modified by fusel salt and waste mother liquor of sodium ferrocyanide as the main sulfur fixation agent and the calcium based natural mineral materials as servicing additives; the experimental results showed the following: (1 Through 10 wt% waste mother liquor of sodium ferrocyanide modifying Bayer red mud, sulfur fixation rate can increase by 13 wt%. (2 Magnesium oxide can obviously improve the sulfur fixation performance of Bayer red mud and up to a maximum sulfur fixation rate of 47 wt% at adding 1 wt% magnesium oxide. (3 Dolomite enhanced the sulfur fixation performances with the sulfur fixation rate of 68 wt% in optimized condition. (4 Vermiculite dust reduced sulfur dioxide during the fixed-sulfur process of modified Bayer red mud, and the desulphurization ration could reach up to a maximum 76 wt% at 950°C. (5 An advanced three-component sulfur fixation agent was investigated, in which the optimized mass ratio of modified Bayer red mud, dolomite, and vermiculite dust was 70 : 28 : 2 in order, and its sulfur fixation efficiency has reached to a maximum 87 wt% under its 20 wt% dosage in the coal.

  7. Liquid waste treatment system. Final report

    International Nuclear Information System (INIS)

    Baker, M.N.; Houston, H.M.

    1999-01-01

    Pretreatment of high-level liquid radioactive waste (HLW) at the West Valley Demonstration Project (WVDP) involved three distinct processing operations: decontamination of liquid HLW in the Supernatant Treatment System (STS); volume reduction of decontaminated liquid in the Liquid Waste Treatment System (LWTS); and encapsulation of resulting concentrates into an approved cement waste form in the Cement Solidification System (CSS). Together, these systems and operations made up the Integrated Radwaste Treatment System (IRTS)

  8. Immobilization in ceramic waste forms of the residues from treatment of mixed wastes

    International Nuclear Information System (INIS)

    Oversby, V.M.; van Konynenburg, R.A.; Glassley, W.E.; Curtis, P.G.

    1993-11-01

    The Environmental Restoration and Waste Management Applied Technology Program at LLNL is developing a Mixed Waste Management Facility to demonstrate treatment technologies that provide an alternative to incineration. As part of that program, we are developing final waste forms using ceramic processing methods for the immobilization of the treatment process residues. The ceramic phase assemblages are based on using Synroc D as a starting point and varying the phase assemblage to accommodate the differences in chemistry between the treatment process residues and the defense waste for which Synroc D was developed. Two basic formulations are used, one for low ash residues resulting from treatment of organic materials contaminated with RCRA metals, and one for high ash residues generated from the treatment of plastics and paper products. Treatment process residues are mixed with ceramic precursor materials, dried, calcined, formed into pellets at room temperature, and sintered at 1150 to 1200 degrees C to produce the final waste form. This paper discusses the chemical composition of the waste streams and waste forms, the phase assemblages that serve as hosts for inorganic waste elements, and the changes in waste form characteristics as a function of variation in process parameters

  9. Hazardous Waste Treatment Facility and skid-mounted treatment systems at Los Alamos

    International Nuclear Information System (INIS)

    Lussiez, G.W.; Zygmunt, S.J.

    1994-01-01

    To centralize treatment, storage, and areas for hazardous wastes, Los Alamos National Laboratory has designed a 1115 m2 hazardous waste treatment facility. The facility will house a treatment room for each of four kinds of wastes: nonradioactive characteristic wastes, nonradioactive listed wastes, radioactive characteristic wastes, and radioactive listed wastes. The facility will be used for repacking labpacks; bulking small organic waste volumes; processing scintillation vials; treating reactives such as lithium hydride and pyrophoric uranium; treating contaminated solids such as barium sand; treating plating wastes and other solutions with heavy metals and oxidizing organics: Separate treatment rooms will allow workers to avoid mixing waste types and prevent cross-contamination. The ventilation air from the treatment areas may contain hazardous or radioactive dust. Gas may also leak from process equipment. The gas treatment process includes separating solids and gases and neutralization or adsorption of the hazardous gases. The ventilation air from each room will first be filtered before being scrubbed in a common gas caustic scrubber on an outside pad. There are two levels of exhaust in each treatment room, one for heavy gases and another for light gases. Several features help mitigate or eliminate hazards due to spills and releases: each treatment room is sealed and under slight negative pressure; each room has its own HEPA filtration; to avoid mixing of incompatible wastes and reagents, portable individual spill-containment trays are used for skids, to limit the danger of spills, the waste is directly transferred from outside storage to the treatment room; to mitigate the consequences of a gas release in the room, mobile hoods are connected to the exhaust-air treatment system; the floor, walls, ceilings, fixtures, ducts, and piping are made of acid-resistant material or are coated

  10. Conflicts concerning sites for waste treatment and waste disposal plants

    International Nuclear Information System (INIS)

    Werbeck, N.

    1993-01-01

    The erection of waste treatment and waste disposal flants increasingly meets with the disapproval of local residents. This is due to three factors: Firstly, the erection and operation of waste treatment plants is assumed to necessarily entail harmful effects and risks, which may be true or may not. Secondly, these disadvantages are in part considered to be non-compensable. Thirdly, waste treatment plants have a large catchment area, which means that more people enjoy their benefits than have to suffer their disadvantages. If residents in the vicinity of such plants are not compensated for damage sustained or harmed in ways that cannot be compensated for it becomes a rational stance for them, while not objecting to waste treatment and waste disposal plants in principle to object to their being in their own neighbourhood. The book comprehensively describes the subject area from an economic angle. The causes are analysed in detail and an action strategy is pointed, out, which can help to reduce acceptance problems. The individual chapters deal with emissions, risk potentials, optimization calculus considering individual firms or persons and groups of two or more firms or persons, private-economy approaches for the solving of site selection conflicts, collective decision-making. (orig./HSCH) [de

  11. Evaluation of Secondary Streams in Mixed Waste Treatment

    International Nuclear Information System (INIS)

    Haywood, Fred F.; Goldsmith, William A.; Allen, Douglas F.; Mezga, Lance J.

    1995-12-01

    The United States Department of Energy (DOE) and its predecessors have generated waste containing radioactive and hazardous chemical components (mixed wastes) for over 50 years. Facilities and processes generating these wastes as well as the regulations governing their management have changed. Now, DOE has 49 sites where mixed waste streams exist. The Federal Facility Compliance Act of 1992 (1) required DOE to prepare and obtain regulatory approval of plans for treating these mixed waste streams. Each of the involved DOE sites submitted its respective plan to regulators in April 1995 (2). Most of the individual plans were approved by the respective regulatory agencies in October 1995. The implementation of these plans has begun accordance with compliance instruments (orders) issued by the cognizant regulatory authority. Most of these orders include milestones that are fixed, firm and enforceable as defined in each compliance order. In many cases, mixed waste treatment that was already being carried out and survived the alternative selection process is being used now to treat selected mixed waste streams. For other waste streams at sites throughout the DOE complex treatment methods and schedules are subject to negotiation as the realties of ever decreasing budgets begin to drive the available options. Secondary wastes generated by individual waste treatment systems are also mixed wastes that require treatment in the appropriate treatment system. These secondary wastes may be solid or liquid waste (or both). For example debris washing will generate wastewater requiring treatment; wastewater treatment, in turn, will generate sludge or other residuals requiring treatment; liquid effluents must meet applicable limits of discharge permits. At large DOE sites, secondary waste streams will be a major influence in optimizing design for primary treatment. Understanding these impacts is important not only foe system design, but also for assurances that radiation releases and

  12. Rad-waste treatment

    International Nuclear Information System (INIS)

    1996-01-01

    The spent fuel coming from Slovak NPPs have partially been transported to the former Soviet Union, and a part of it is stored in an interim spent fuel wet storage. In compliance with the worldwide practices, further medium-term possibilities of storing in dry storages are under preparation. Disposal of a spent fuel and other high-level active wastes in a deep geological formation repository is the final solution. At present, there are geological investigations of possible sites in progress in Slovakia. Mochovce repository is a factory for a final disposal of compacted low and intermediate level radioactive wastes coming from the Slovak NPPs. This is a near-surface facility of a construction similar to the one used for disposal of radioactive wastes in France, Spain, Japan, Czech Republic, U.S.A, etc. Quality of the design, construction and functioning of the Mochovce's repository was assessed by an international team of experts within a special IAEA programme (WATRP). Having familiarized with the final report of the IAEA mission, Nuclear Regulatory Authority of the Slovak Republic (NRA SR) issued its position early in 1995, in which NRA SR required additional adjustment of the repository itself. Based on the NRA SR's position, Mochovce NPP invited experts from a number of institutions in September 1995 to discuss the NRA SR's requirements. Following was recommended by the experts: (1) to perform a complementary engineering-geological investigation on the site, (2) to use geophysical methods to verify existence of geological faults. In the next part a radioactive wastes that were treated at radioactive waste treatment lines in 1995 are listed. In 1995, the Chief Inspector of NRA SR issued an instruction that radioactive waste department should start inspections of radioactive waste treatment right in hospitals, research institutes and industries. Therefore, a total of 14 such workplaces were incorporated into a plan of inspections in 1995

  13. Expediting the commercial disposal option: Low-level radioactive waste shipments from the Mound Plant

    Energy Technology Data Exchange (ETDEWEB)

    Rice, S.; Rothman, R.

    1995-12-31

    In April, Envirocare of Utah, Inc., successfully commenced operation of its mixed waste treatment operation. A mixed waste which was (a) radioactive, (b) listed as a hazardous waste under the Resource Conservation and Recovery Act (RCRA), and (c) prohibited from land disposal was treated using Envirocare`s full-scale Mixed Waste Treatment Facility. The treatment system involved application of chemical fixation/stabilization technologies to reduce the leachability of the waste to meet applicable concentration-based RCRA treatment standards. In 1988, Envirocare became the first licensed facility for the disposal of naturally occurring radioactive material. In 1990, Envirocare received a RCRA Part B permit for commercial mixed waste storage and disposal. In 1994, Envirocare was awarded a contract for the disposal of DOE mixed wastes. Envirocare`s RCRA Part B permit allows for the receipt, storage, treatment, and disposal of mixed wastes that do not meet the land-disposal treatment standards of 40 CFR (Code of Federal Regulations) 268. Envirocare has successfully received, managed, and disposed of naturally occurring radioactive material, low-activity radioactive waste, and mixed waste from government and private generators.

  14. Treatability study of absorbent polymer waste form for mixed waste treatment

    International Nuclear Information System (INIS)

    Herrmann, S. D.; Lehto, M. A.; Stewart, N. A.; Croft, A. D.; Kern, P. W.

    2000-01-01

    A treatability study was performed to develop and characterize an absorbent polymer waste form for application to low level (LLW) and mixed low level (MLLW) aqueous wastes at Argonne National Laboratory-West (ANL-W). In this study absorbent polymers proved effective at immobilizing aqueous liquid wastes in order to meet Land Disposal Restrictions for subsurface waste disposal. Treatment of aqueous waste with absorbent polymers provides an alternative to liquid waste solidification via high-shear mixing with clays and cements. Significant advantages of absorbent polymer use over clays and cements include ease of operations and waste volume minimization. Absorbent polymers do not require high-shear mixing as do clays and cements. Granulated absorbent polymer is poured into aqueous solutions and forms a gel which passes the paint filter test as a non-liquid. Pouring versus mixing of a solidification agent not only eliminates the need for a mixing station, but also lessens exposure to personnel and the potential for spread of contamination from treatment of radioactive wastes. Waste minimization is achieved as significantly less mass addition and volume increase is required of and results from absorbent polymer use than that of clays and cements. Operational ease and waste minimization translate into overall cost savings for LLW and MLLW treatment

  15. Commercial mixed waste treatment and disposal

    International Nuclear Information System (INIS)

    Vance, J.K.

    1994-01-01

    At the South Clive, Utah, site, Envirocare of Utah, Inc., (Envirocare), currently operates a commercial low-activity, low-level radioactive waste facility, a mixed waste RCRA Part B storage and disposal facility, and an 11e.(2) disposal facility. Envirocare is also in the process of constructing a Mixed Waste Treatment Facility. As the nation's first and only commercial treatment and disposal facility for such waste, the information presented in this segment will provide insight into their current and prospective operations

  16. A perspective of hazardous waste and mixed waste treatment technology at the Savannah River Site

    International Nuclear Information System (INIS)

    England, J.L.; Venkatesh, S.; Bailey, L.L.; Langton, C.A.; Hay, M.S.; Stevens, C.B.; Carroll, S.J.

    1991-01-01

    Treatment technologies for the preparation and treatment of heavy metal mixed wastes, contaminated soils, and mixed mercury wastes are being considered at the Savannah River Site (SRS), a DOE nuclear material processing facility operated by Westinghouse Savannah River Company (WSRC). The proposed treatment technologies to be included at the Hazardous Waste/Mixed Waste Treatment Building at SRS are based on the regulatory requirements, projected waste volumes, existing technology, cost effectiveness, and project schedule. Waste sorting and size reduction are the initial step in the treatment process. After sorting/size reduction the wastes would go to the next applicable treatment module. For solid heavy metal mixed wastes the proposed treatment is macroencapsulation using a thermoplastic polymer. This process reduces the leachability of hazardous constituents from the waste and allows easy verification of the coating integrity. Stabilization and solidification in a cement matrix will treat a wide variety of wastes (i.e. soils, decontamination water). Some pretreatments may be required (i.e. Ph adjustment) before stabilization. Other pretreatments such as soil washing can reduce the amount of waste to be stabilized. Radioactive contaminated mercury waste at the SRS comes in numerous forms (i.e. process equipment, soils, and lab waste) with the required treatment of high mercury wastes being roasting/retorting and recovery. Any unrecyclable radioactive contaminated elemental mercury would be amalgamated, utilizing a batch system, before disposal

  17. Treatment of waste

    International Nuclear Information System (INIS)

    1981-01-01

    A method of treating radioactive waste to substantially reduce the volume and which is especially useful in the treatment of material which includes radioactive halogens such as 131 I, is described. A fluidised bed incinerator and calciner are used to reduce all the liquid and combustible solid waste to anhydrous granular solids, all of which is carried by fluidizing gases into an off-gas system designed for their collection. (U.K.)

  18. 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.)

  19. Mixed and Low-Level Waste Treatment Facility project

    International Nuclear Information System (INIS)

    1992-04-01

    Mixed and low-level wastes generated at the Idaho National Engineering Laboratory (INEL) are required to be managed according to applicable State and Federal regulations, and Department of Energy Orders that provide for the protection of human health and the environment. The Mixed and Low-Level Waste Treatment Facility Project was chartered in 1991, by the Department of Energy to provide treatment capability for these mixed and low-level waste streams. The first project task consisted of conducting engineering studies to identify the waste streams, their potential treatment strategies, and the requirements that would be imposed on the waste streams and the facilities used to process them. The engineering studies, initiated in July 1991, identified 37 mixed waste streams, and 55 low-level waste streams. This report documents the waste stream information and potential treatment strategies, as well as the regulatory requirements for the Department of Energy-owned treatment facility option. The total report comprises three volumes and two appendices. This report consists of Volume 1, which explains the overall program mission, the guiding assumptions for the engineering studies, and summarizes the waste stream and regulatory information, and Volume 2, the Waste Stream Technical Summary which, encompasses the studies conducted to identify the INEL's waste streams and their potential treatment strategies

  20. Scaphoid Waist Internal Fixation for Fractures Trial (SWIFFT) protocol: a pragmatic multi-centre randomised controlled trial of cast treatment versus surgical fixation for the treatment of bi-cortical, minimally displaced fractures of the scaphoid waist in adults.

    Science.gov (United States)

    Dias, Joseph; Brealey, Stephen; Choudhary, Surabhi; Cook, Liz; Costa, Matthew; Fairhurst, Caroline; Hewitt, Catherine; Hodgson, Stephen; Jefferson, Laura; Jeyapalan, Kanagaratnam; Keding, Ada; Leighton, Paul; Rangan, Amar; Richardson, Gerry; Rothery, Claire; Taub, Nicholas; Thompson, John; Torgerson, David

    2016-06-04

    A scaphoid fracture is the most common type of carpal fracture affecting young active people. The optimal management of this fracture is uncertain. When treated with a cast, 88 to 90 % of these fractures unite; however, for the remaining 10-12 % the non-union almost invariably leads to arthritis. The alternative is surgery to fix the scaphoid with a screw at the outset. We will conduct a randomised controlled trial (RCT) of 438 adult patients with a "clear" and "bicortical" scaphoid waist fracture on plain radiographs to evaluate the clinical effectiveness and cost-effectiveness of plaster cast treatment (with fixation of those that fail to unite) versus early surgical fixation. The plaster cast treatment will be immobilisation in a below elbow cast for 6 to 10 weeks followed by mobilisation. If non-union is confirmed on plain radiographs and/or Computerised Tomogram at 6 to 12 weeks, then urgent surgical fixation will be performed. This is being compared with immediate surgical fixation with surgeons using their preferred technique and implant. These treatments will be undertaken in trauma units across the United Kingdom. The primary outcome and end-point will be the Patient Rated Wrist Evaluation (a patient self-reported assessment of wrist pain and function) at 52 weeks and also measured at 6, 12, 26 weeks and 5 years. Secondary outcomes include an assessment of radiological union of the fracture; quality of life; recovery of wrist range and strength; and complications. We will also qualitatively investigate patient experiences of their treatment. Scaphoid fractures are an important public health problem as they predominantly affect young active individuals in the more productive working years of their lives. Non-union, if untreated, can lead to arthritis which can disable patients at a very young age. There is a rapidly increasing trend for immediate surgical fixation of these fractures but there is insufficient evidence from existing RCTs to support

  1. Clinical efficacy and safety of limited internal fixation combined with external fixation for Pilon fracture: A systematic review and meta-analysis

    OpenAIRE

    Zhang, Shaobo; Zhang, Yibao; Wang, Shenghong; Zhang, Hua; Liu, Peng; Zhang, Wei; Ma, Jing-Lin; Wang, Jing

    2017-01-01

    Purpose: To compare the clinical efficacy and complications of limited internal fixation combined with external fixation (LIFEF) and open reduction and internal fixation (ORIF) in the treatment of Pilon fracture. Methods: We searched databases including Pubmed, Embase, Web of science, Cochrane Library and China Biology Medicine disc for the studies comparing clinical efficacy and complications of LIFEF and ORIF in the treatment of Pilon fracture. The clinical efficacy was evaluated by the ...

  2. Unstable metacarpal and phalangeal fractures: treatment by internal fixation using AO mini-fragment plates and screws.

    Science.gov (United States)

    Mumtaz, Mohammad Umar; Farooq, Muneer Ahmad; Rasool, Altaf Ahmad; Kawoosa, Altaf Ahmad; Badoo, Abdul Rashid; Dhar, Shabir Ahmad

    2010-07-01

    Accurate open reduction and internal fixation for metacarpal and phalangeal fractures of the hand is required in less than 5% of the patients; otherwise, closed treatment techniques offer satisfactory results in most of these cases as these fractures are stable either before or after closed reduction. AO mini-fragment screws and plates, when used in properly selected cases, can provide rigid fixation, allowing early mobilization of joints and hence good functional results while avoiding problems associated with protruding K-wires and immobilization. The advantages of such internal fixation urged us to undertake such a study in our state where such hand injuries are commonly seen. Forty patients with 42 unstable metacarpal and phalangeal fractures were treated with open reduction and internal fixation using AO mini-fragment screws and plates over a period of three years in a prospective manner. The overall results were good in 78.5% of cases, fair in 19% of cases and poor in 2.5% of cases, as judged according to the criteria of the American Society for Surgery of the Hand. This technique is a reasonable option for treating unstable metacarpal and phalangeal fractures as it provides a highly rigid fixation, which is sufficient to allow early mobilization of the adjacent joints, thus helping to achieve good functional results.

  3. Treatment of alpha bearing wastes

    International Nuclear Information System (INIS)

    1988-01-01

    This report deals with the current state of the art of alpha waste treatment, which is an integral part of the overall nuclear waste management system. The International Atomic Energy Agency (IAEA) defines alpha bearing waste as 'waste containing one or more alpha emitting radionuclides, usually actinides, in quantities above acceptable limits'. The limits are established by national regulatory bodies. The limits above which wastes are considered as alpha contaminated refer to the concentrations of alpha emitters that need special consideration for occupational exposures and/or potential safety, health, or environmental impact during one or more steps from generation through disposal. Owing to the widespread use of waste segregation by source - that is, based upon the 'suspect origin' of the material - significant volumes of waste are being handled as alpha contaminated which, in fact, do not require such consideration by reason of risk or environmental concern. The quantification of de minimis concepts by national regulatory bodies could largely contribute to the safe reduction of waste volumes and associated costs. Other factors which could significantly contribute to the reduction of alpha waste arisings are an increased application of assaying and sorting, instrumentation and the use of feedback mechanisms to control or modify the processes which generate these wastes. Alpha bearing wastes are generated during fabrication and reprocessing of nuclear fuels, decommissioning of alpha contaminated facilities, and other activities. Most alpha wastes are contact handled, but a small portion may require shielding or remote handling because of high levels of neutron (n), beta (β), or gamma (γ) emissions associated with the waste material. This report describes the sources and characteristics of alpha wastes and strategies for alpha waste management. General descriptions of treatment processes for solid and liquid alpha wastes are included. 71 refs, 14 figs, 9 tabs

  4. Cyanide wastes treatment by bioremediation

    International Nuclear Information System (INIS)

    Deloya Martinez, Alma

    2012-01-01

    The results of the development of an autochthonous consortium of degrader microorganisms of the cyanide for the application in the biological treatment of the dangerous wastes of cyanide, were presented. The autochthonous microorganisms obtained were lyophilized in different protective environments, such as gelatin and lactose broth at different temperatures (-35, -45, -55 and -65). A pretreatment method in slurry was applied for the preliminary treatment of the cyanide wastes: for the preliminary leaching of the waste, with periods between 3 and 5 days and a posterior treatment, by aerated lagoons, applying the consortium of lyophilized microorganisms. Eight different lyophilized were obtained in different temperature conditions and with two lyophilization protective media that have presented excellent recovery at six months of lyophilization. The consortium of lyophilized microorganisms has presented 70 to 80 percent of viability, with cyanide removal percentages higher than 95% and it can be conserved active for a prolonged time (for years). The lyophilized microorganisms can be applied in the biodegradation of the cyanide wastes from the gold mines or any other cyanide waste such as metal electroplanting baths, as well as from jewelry manufacturing. (author) [es

  5. Mixed-waste treatment -- What about the residuals?

    International Nuclear Information System (INIS)

    Carlson, T.; Carpenter, C.; Cummins, L.; Haas, P.; MacInnis, J.; Maxwell, C.

    1993-01-01

    Incineration currently is the best demonstrated available technology for the large inventory of U.S. Department of Energy (DOE) mixed waste. However, molten salt oxidation (MSO) is an alternative thermal treatment technology with the potential to treat a number of these wastes. Of concern for both technologies is the final waste forms, or residuals, that are generated by the treatment process. An evaluation of the two technologies focuses on 10 existing DOE waste streams and current hazardous-waste regulations, specifically for the delisting of ''derived-from'' residuals. Major findings include that final disposal options are more significantly impacted by the type of waste treated and existing regulations than by the type of treatment technology; typical DOE waste streams are not good candidates for delisting; and mass balance calculations indicate that MSO and incineration generate similar quantities (dry) and types of residuals

  6. Sorption and fixation of large cations by shale formations

    International Nuclear Information System (INIS)

    Brindley, G.W.

    1977-01-01

    Large cations such as Cs + are preferentially sorbed and partially fixed by fine-grained 2 : 1 type layer silicates such as micas, vermiculites, smectites and various mixed-layer minerals. Since these minerals are common constituents of many shale formations, these formations may provide suitable location for the burial of radioactive waste containers. However, the usual investigations of cation sorption and fixation must be extended to the conditions likely to develop in the vicinity of buried radioactive waste. Prior to possible leakage from buried containers, elevated temperatures around the burial site will develop leading to hydrothermal modification of the surrounding mineralogy. A range of temperature and of mineralogy must be envisaged. If and when leakage occurs, an outward diffusion of radioactive ions will occur by solvation in the fluids in the shale. The ratio of radioactive ions/normal ions will diminish outwards from the source. At near distances from the source high temperature modifications of the clay minerals and high concentrations of radioactive cations may lead to saturation of the fixation capacity. At greater distances, little or no thermal modification of the clay minerals and lower concentrations of ions will permit maximum sorption and fixation

  7. Treatment of liquid radioactive waste: Precipitation

    International Nuclear Information System (INIS)

    Gompper, K.

    1982-01-01

    After introductory remarks about waste types to be treated, specific treatment methods are discussed and examples are given for treatment processes carried out with different types of liquid wastes from nuclear power plants, research centers and fuel reprocessing plants. (RW)

  8. Waste management and treatment or disguised disposal?

    International Nuclear Information System (INIS)

    Drum, D.A.; Lauber, J.

    1992-01-01

    A number of political action groups, environmental groups, and waste management industries have purposely used medical waste data and municipal solid waste test results to mislead public officials and communities. Waste management schemes and waste treatment technologies must be measured and compared by the same test criteria. For example, anti-incineration groups often use the toxic dioxin/furan data and/or toxic metal arguments to oppose waste-to-energy incineration technologies. Comparable test data on waste management techniques such as waste composting, autoclaving, and landfilling are either nonexistent or often inappropriately applied. Integrated waste management systems require technologically accurate and complete data, environmentally-appropriate designed systems, and fiscal responsibility. The primary emphasis of waste management and treatment practices must be directed toward minimization, reuse, destruction, and detoxification of municipal solid wastes and medical wastes. The issues and alternatives will be examined

  9. Treatment of midshaft clavicular nonunion with plate fixation and autologous bone grafting

    DEFF Research Database (Denmark)

    Olsen, Bo Sanderhoff; Vaesel, M T; Søjbjerg, Jens Ole

    1995-01-01

    We studied the results of 16 consecutive midshaft clavicular nonunions operated on at the Shoulder and Elbow Clinic during the period from 1990 to 1993. All patients were treated with rigid 3.5 mm plate fixation and autologous cancellous bone grafting. Union of the fractures was achieved in all...... except one case, with a reconstruction ratio (restoration of bone length) of 0.96 (range 0.88 to 1.03). At follow-up 12 of 16 patients had returned to their preinjury activity level and according to the Constant score had obtained an excellent result. Two patients were graded as good, one as fair......, and one had a failure. Thirteen of 16 patients were satisfied with the cosmetic outcome, assessing their cosmetic result as either good or excellent. Rigid plate fixation and restoration of clavicular length with autologous cancellous bone graft is recommended for the treatment of symptomatic clavicular...

  10. The fixation of radioactive wastes in cement

    International Nuclear Information System (INIS)

    Kulichenko, V.V.; Dukhovich, F.S.; Volkova, O.I.; Boyarinova, M.V.

    1976-01-01

    The authors study the leaching behaviour of the main long-lived fission products 90 Sr and 137 Cs. It is found that 90 Sr and 137 Cs have high elution values, namely (2-12) x 10 -2 resp. (2-6) x 10 -2 g/cm 2 /24h, independently of the type of waste. On the basis of these results, maximum concentrations for the solutions in the cement/solution mixtures are proposed. Further studies relate to the formation of radiolysis gas in the waste fixed to cement. Experiments are described to make use of the empty space in the containers, filled with solid waste by filling them with mixtures of cement and liquid radioactive waste of 10 -4 to 1- 6 Ci. The ratio solution/cement should amount to 0.5. The containers are then buried underground. This method of combined waste storage helped to reduce the cost for the storage of liquid waste by about 40-50%. (RB) [de

  11. Fusion Surgery Required for Recurrent Pediatric Atlantoaxial Rotatory Fixation after Failure of Temporary Fixation with Instrumentation

    Directory of Open Access Journals (Sweden)

    Yoshiyuki Matsuyama

    2017-01-01

    Full Text Available In cases of chronic irreducible and recurrent unstable atlantoaxial rotatory fixation (AARF, closed reduction and its maintenance are often unsuccessful, requiring surgical treatment. The purpose of the present report is to describe a rare case of pediatric AARF that required multiple treatments. A 6-year-old boy was diagnosed as having type 2 AARF. After conservative treatment, the patient was treated with temporary fixation surgery (C1-C2 Magerl without a bone graft in consideration of motion preservation after screw removal. AARF recurred after the screw removal and required fusion surgery (Magerl–Brooks with an iliac bone graft. Ultimately, bone union was achieved and the screws were removed 11 months after the surgery. We recommend surgeons be cautious when choosing temporary fixation surgery for AARF in small children. Further investigation is needed to determine the optimal time before screw removal.

  12. Treatment of radioactive wastes containing plutonium

    International Nuclear Information System (INIS)

    Orlando, O.S.; Aparicio, G.; Greco, L.; Orosco, E.H.; Cassaniti, P.; Salguero, D.; Toubes, B.; Perez, A.E.; Menghini, J.E.; Esteban, A.; Adelfang, P.

    1987-01-01

    The radioactive wastes generated in the process of manufacture and control of experimental fuel rods of mixed oxides, (U,Pu)O 2 , require an specific treatment due to the plutonium content. The composition of liquid wastes, mostly arising from chemical checks, is variable. The salt content, the acidity, and the plutonium and uranium content are different, which makes necessary a chemical treatment before the inclusion in concrete. The solid waste, such as neoprene gloves, PVC sleeves, filter paper, disposable or broken laboratory material, etc. are also included in concrete. In this report the methods used to dispose of wastes at Alpha Facility are described. With regard to the liquid wastes, the glove box built to process them is detailed, as well as the applied chemical treatment, including neutralization, filtration and later solidification. As for the solid wastes, it is described the cementation method consisting in introducing them into an expanded metal matrix, of the basket type, that contains as a concentric drum of 200 liter capacity which is smaller than the matrix, and the filling with wet cement mortar. (Author)

  13. Temporary Stabilization with External Fixator in ‘Tripolar’ Configuration in Two Steps Treatment of Tibial Pilon Fractures

    Science.gov (United States)

    Daghino, Walter; Messina, Marco; Filipponi, Marco; Alessandro, Massè

    2016-01-01

    Background: The tibial pilon fractures represent a complex therapeutic problem for the orthopedic surgeon, given the frequent complications and outcomes disabling. The recent medical literature indicates that the best strategy to reduce amount of complications in tibial pilon fractures is two-stages procedure. We describe our experience in the primary stabilization of these fractures. Methods: We treated 36 cases with temporary external fixation in a simple configuration, called "tripolar": this is an essential structure (only three screws and three rods), that is possible to perform even without the availability of X-rays and with simple anesthesia or sedation. Results: We found a sufficient mechanical stability for the nursing post-operative, in absence of intraoperative and postoperative problems. The time between trauma and temporary stabilization ranged between 3 and 144 hours; surgical average time was 8.4 minutes. Definitive treatment was carried out with a delay of a minimum of 4 and a maximum of 15 days from the temporary stabilization, always without problems, both in case of ORIF (open reduction, internal fixation) or circular external fixation Conclusion: Temporary stabilization with external fixator in ‘tripolar’ configuration seems to be the most effective strategy in two steps treatment of tibial pilon fractures. These preliminary encouraging results must be confirmed by further studies with more cases. PMID:27123151

  14. Unilateral fixation for treatment of occipitocervical instability in children with congenital vertebral anomalies of the craniocervical junction.

    Science.gov (United States)

    Mazur, Marcus D; Ravindra, Vijay M; Brockmeyer, Douglas L

    2015-04-01

    OBJECT Patients with occipitocervical (OC) instability from congenital vertebral anomalies (CVAs) of the craniocervical junction (CCJ) often have bony abnormalities that make instrumentation placement difficult. Within this patient population, some bilateral instrumentation constructs either fail or are not feasible, and a unilateral construct must be used. The authors describe the surgical management and outcomes of this disorder in patients in whom unilateral fixation constructs were used to treat OC instability. METHODS From a database of OC fusion procedures, the authors identified patients who underwent unilateral fixation for the management of OC instability. Patient characteristics, surgical details, and radiographic outcomes were reviewed. In each patient, CT scans were performed at least 4 months after surgery to evaluate for fusion. RESULTS Eight patients with CVAs of the CCJ underwent unilateral fixation for the treatment of OC instability. For 4 patients, the procedure occurred after a bilateral OC construct failed or infection forced hardware removal. For the remainder, it was the primary procedure. Two patients required reoperation for hardware revision and 1 developed nonunion requiring revision of the bone graft. Ultimately, 7 patients demonstrated osseous fusion on CT scans and 1 had a stable fibrous union. CONCLUSIONS These findings demonstrate that a unilateral OC fixation is effective for the treatment of OC instability in children with CVAs of the CCJ in whom bilateral screw placement fails or is not feasible.

  15. Mixed and low-level waste treatment facility project. Volume 3, Waste treatment technologies (Draft)

    Energy Technology Data Exchange (ETDEWEB)

    1992-04-01

    The technology information provided in this report is only the first step toward the identification and selection of process systems that may be recommended for a proposed mixed and low-level waste treatment facility. More specific information on each technology will be required to conduct the system and equipment tradeoff studies that will follow these preengineering studies. For example, capacity, maintainability, reliability, cost, applicability to specific waste streams, and technology availability must be further defined. This report does not currently contain all needed information; however, all major technologies considered to be potentially applicable to the treatment of mixed and low-level waste are identified and described herein. Future reports will seek to improve the depth of information on technologies.

  16. Integrated treatment process of hazardous and mixed wastes

    International Nuclear Information System (INIS)

    Shibuya, M.; Suzuki, K.; Fujimura, Y.; Nakashima, T.; Moriya, Y.

    1993-01-01

    An integrated waste treatment system was studied based on technologies developed for the treatment of liquid radioactive, organic, and aqueous wastes containing hazardous materials and soils contaminated with heavy metals. The system consists of submerged incineration, metal ion fixing and stabilization, and soil washing treatments. Introduction of this system allows for the simultaneous processing of toxic waste and contaminated soils. Hazardous organic wastes can be decomposed into harmless gases, and aqueous wastes can be converted into a dischargeable effluent. The contaminated soil is backfilled after the removal of toxic materials. Experimental data show that the integration system is practical for complicated toxic wastes

  17. Challenges when Performing Economic Optimization of Waste Treatment

    DEFF Research Database (Denmark)

    Juul, Nina; Münster, Marie; Ravn, Hans

    2011-01-01

    New investments in waste treatment facilities are needed due to a number of factors including continuously increasing waste amounts, political demands for efficient utilization of the waste resources in terms of recycling or energy production, and decommissioning of existing waste treatment...... facilities due to age and stricter environmental regulation. Optimization models can assist in ensuring that these investment strategies will be economically feasible. Various economic optimization models for waste treatment have been developed which focus on different parameters. Models focusing...... in multi criteria analysis have been developed. A thorough updated review of the existing models is presented and the main challenges and the crucial parameters to take into account when assessing the economic performance of waste treatment alternatives are identified. The review article will assist both...

  18. Fixation of displaced subcapital femoral fractures. Compression screw fixation versus double divergent pins.

    Science.gov (United States)

    Christie, J; Howie, C R; Armour, P C

    1988-03-01

    One hundred and twenty-seven consecutive patients with displaced subcapital fractures of the femoral neck (Garden Grade III or IV) all under 80 years of age and independently mobile, were randomly allocated to fixation with either double divergent pins or a single sliding screw-plate device. The incidence of non-union and infection in the sliding screw-plate group was significantly higher, and we believe that when internal fixation is considered appropriate multiple pinning should be used. Mobility after treatment was disappointing in about half of the patients, and we feel that internal fixation can only be justified in patients who are physiologically well preserved and who maintain a high level of activity.

  19. Management of transuranic wastes throughout the world

    International Nuclear Information System (INIS)

    Lakey, L.T.; Christensen, H.; De Jonghe, P.; Frejaville, G.; Lavie, J.M.; Thackrah, D.G.

    1983-01-01

    Transuranic (TRU) wastes are those radioactive wastes, except spent fuel and high-level wastes, that are contaminated with sufficient long-lived, alpha-emitting nuclides that the decay to innocuous levels in engineered storage structures or shallow-land burial sites cannot be used as a disposal method. This class of waste is produced principally during spent fuel reprocessing, recycle fuel fabrication, and weapons material production. At least ten countries are involved in operations producing this class of waste, which represents a small fraction of the alpha-emitting nuclides in the world's inventory and of the total volume of radioactive wastes produced in nuclear activities. No consensus has been reached on a numerical definition; definitions in use vary from >0.03 to >1000 nCi transuranium radionuclides per gram of waste (TRU/g). The definitions are presently used to separate wastes going to sea dumping or shallow-land burial from those requiring greater isolation. All countries emphasize plutonium recovery and volume reduction in their plans for treating TRU wastes. Incineration is the most prevalent treatment in use. When fixation is used, cement and bitumen are the preferred fixation media. All high-concentration TRU wastes are now being placed in interim storage. No TRU wastes are presently being disposed except the low-concentration wastes being dumped at sea by Belgium and the United Kingdom and those being injected into geologic strata by the United States (Oak Ridge National Laboratory) and the USSR. All countries prefer and are planning to use deep geologic repositories for final disposal of TRU wastes. According to present schedules, the Waste Isolation Pilot Plant (WIPP) facility in the United States, with a scheduled startup date of 1989, will be the first operating repository since the closure of the Federal Republic of Germany's Asse Salt Mine in 1977

  20. Sodium-Bearing Waste Treatment Alternatives Implementation Study

    Energy Technology Data Exchange (ETDEWEB)

    Charles M. Barnes; James B. Bosley; Clifford W. Olsen

    2004-07-01

    The purpose of this document is to discuss issues related to the implementation of each of the five down-selected INEEL/INTEC radioactive liquid waste (sodium-bearing waste - SBW) treatment alternatives and summarize information in three main areas of concern: process/technical, environmental permitting, and schedule. Major implementation options for each treatment alternative are also identified and briefly discussed. This report may touch upon, but purposely does not address in detail, issues that are programmatic in nature. Examples of these include how the SBW will be classified with respect to the Nuclear Waste Policy Act (NWPA), status of Waste Isolation Pilot Plant (WIPP) permits and waste storage availability, available funding for implementation, stakeholder issues, and State of Idaho Settlement Agreement milestones. It is assumed in this report that the SBW would be classified as a transuranic (TRU) waste suitable for disposal at WIPP, located in New Mexico, after appropriate treatment to meet transportation requirements and waste acceptance criteria (WAC).

  1. Biomechanical Evaluation of Standard Versus Extended Proximal Fixation Olecranon Plates for Fixation of Olecranon Fractures.

    Science.gov (United States)

    Boden, Allison L; Daly, Charles A; Dalwadi, Poonam P; Boden, Stephanie A; Hutton, William C; Muppavarapu, Raghuveer C; Gottschalk, Michael B

    2018-01-01

    Small olecranon fractures present a significant challenge for fixation, which has resulted in development of plates with proximal extension. Olecranon-specific plates with proximal extensions are widely thought to offer superior fixation of small proximal fragments but have distinct disadvantages: larger dissection, increased hardware prominence, and the increased possibility of impingement. Previous biomechanical studies of olecranon fracture fixation have compared methods of fracture fixation, but to date there have been no studies defining olecranon plate fixation strength for standard versus extended olecranon plates. The purpose of this study is to evaluate the biomechanical utility of the extended plate for treatment of olecranon fractures. Sixteen matched pairs of fresh-frozen human cadaveric elbows were used. Of the 16, 8 matched pairs received a transverse osteotomy including 25% and 8 including 50% of the articular surface on the proximal fragment. One elbow from each pair was randomly assigned to a standard-length plate, and the other elbow in the pair received the extended-length plate, for fixation of the fracture. The ulnae were cyclically loaded and subsequently loaded to failure, with ultimate load, number of cycles, and gap formation recorded. There was no statistically significant difference between the standard and extended fixation plates in simple transverse fractures at either 25% or 50% from the proximal most portion of the articular surface of the olecranon. Standard fixation plates are sufficient for the fixation of small transverse fractures, but caution should be utilized particularly with comminution and nontransverse fracture patterns.

  2. Organic waste treatment with organically modified clays

    International Nuclear Information System (INIS)

    Evans, J.C.; Pancoski, S.E.; Alther, G.

    1989-01-01

    The use of organically modified clays in hazardous waste management applications offers a significant new and untapped potential. These clays may be used in the stabilization of organic wastes and organically contaminated soils, for waste water treatment, for oil spill control, for liner systems beneath fuel oil storage tanks, and as a component within liner systems of hazardous waste storage treatment and disposal facilities. Organically modified clays (organophilic clays) may be employed in each of these systems to adsorb organic waste constituents, enhancing the performance of the applications

  3. 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

  4. Evaluation of waste treatment technologies by LLWDDD [Low-Level Waste Disposal Development and Demonstration] Programs

    International Nuclear Information System (INIS)

    Kennerly, J.M.; Williams, L.C.; Dole, L.R.; Genung, R.K.

    1987-01-01

    Waste treatments are divided into four categories: (1) volume reduction; (2) conditioning to improve waste form performance; (3) segregation to achieve waste reduction; and (4) separation to remove radioactive (or hazardous) constituents. Two waste treatment demonstrations are described. In the first, volume reduction by mechanical means was achieved during the supercompaction of 300 55-gal drums of solid waste at ORNL. In the second demonstration, conditioning of waste through immobilization and packaging to improve the performance of the waste form is being evaluated. The final section of this paper describes potential scenarios for the management of uranium-contaminated wastes at the Y-12 Plant in Oak Ridge and emphasizes where demonstrations of treatment technology will be needed to implement the scenarios. Separation and thermal treatment are identified as the principal means for treating these wastes. 15 figs

  5. Alpha wastes treatment

    International Nuclear Information System (INIS)

    Thouvenot, P.

    2000-01-01

    Alter 2004, the alpha wastes issued from the Commissariat a l'Energie Atomique installations will be sent to the CEDRA plant. The aims of this installation are decontamination and wastes storage. Because of recent environmental regulations concerning ozone layer depletion, the use of CFC 113 in the decontamination unit, as previously planned, is impossible. Two alternatives processes are studied: the AVD process and an aqueous process including surfactants. Best formulations for both processes are defined issuing degreasing kinetics. It is observed that a good degreasing efficiency is linked to a good decontamination efficiency. Best results are obtained with the aqueous process. Furthermore, from the point of view of an existing waste treatment unit, the aqueous process turns out to be more suitable than the AVD process. (author)

  6. Nuclear waste management at DOE

    International Nuclear Information System (INIS)

    Perge, A.F.

    1979-01-01

    DOE is responsible for interim storage for some radioactive wastes and for the disposal for most of them. Of the wastes that have to be managed a significant part are a result of treatment systems and devices for cleaning gases. The long term waste management objectives place minimal reliance on surveillance and maintenance. Thus, the concerns about the chemical, thermal, and radiolytic degradation of wastes require technology for converting the wastes to forms acceptable for long term isolation. The strategy of the DOE airborne radioactive waste management program is to increase the service life and reliability of filters; to reduce filter wastes; and in anticipation of regulatory actions that would require further reductions in airborne radioactive releases from defense program facilities, to develop improved technology for additional collection, fixation, and long-term management of gaseous wastes. Available technology and practices are adequate to meet current health and safety standards. The program is aimed primarily at cost effective improvements, quality assurance, and the addition of new capability in areas where more restrictive standards seem likely to apply in the future

  7. Waste treatment

    International Nuclear Information System (INIS)

    Davies, D.; Hooper, E.W.

    1981-01-01

    In the treatment of wastes, such as liquid radioactive effluents, it is known to remove radionuclides by successive in situ precipitation of cobalt sulphide, an hydroxide, barium sulphate and a transition element ferrocyanide, followed by separation of the thereby decontaminated effluent. In this invention, use is made of precipitates such as obtained above in the treatment of further fresh liquid radioactive effluent, when it is found that the precipitates have additional capacity for extracting radionuclides. The resulting supernatant liquor may then be subjected to a further precipitation treatment such as above. Decontamination factors for radionuclides of Ce, Ru, Sr and Cs have been considerably enhanced. (author)

  8. Life cycle assessment of electronic waste treatment.

    Science.gov (United States)

    Hong, Jinglan; Shi, Wenxiao; Wang, Yutao; Chen, Wei; Li, Xiangzhi

    2015-04-01

    Life cycle assessment was conducted to estimate the environmental impact of electronic waste (e-waste) treatment. E-waste recycling with an end-life disposal scenario is environmentally beneficial because of the low environmental burden generated from human toxicity, terrestrial ecotoxicity, freshwater ecotoxicity, and marine ecotoxicity categories. Landfill and incineration technologies have a lower and higher environmental burden than the e-waste recycling with an end-life disposal scenario, respectively. The key factors in reducing the overall environmental impact of e-waste recycling are optimizing energy consumption efficiency, reducing wastewater and solid waste effluent, increasing proper e-waste treatment amount, avoiding e-waste disposal to landfill and incineration sites, and clearly defining the duties of all stakeholders (e.g., manufacturers, retailers, recycling companies, and consumers). Copyright © 2015 Elsevier Ltd. All rights reserved.

  9. EPA/DOE joint efforts on mixed waste treatment

    International Nuclear Information System (INIS)

    Lee, C.C.; Huffman, G.L.; Nalesnik, R.P.

    1995-01-01

    Under the requirements of the Federal Facility Compliance Act (FFCA), the Department of Energy (DOE) is directed to develop treatment plans for their stockpile of wastes generated at their various sites. As a result, DOE is facing the monumental problem associated with the treatment and ultimate disposal of their mixed (radioactive and hazardous) waste. Meanwhile, the Environmental Protection Agency (EPA) issued a final open-quotes Hazardous Waste Combustion Strategyclose quotes in November 1994. Under the Combustion Strategy, EPA permit writers have been given the authority to use the Omnibus Provision of the Resource Conservation and Recovery Act (RCRA) to impose more stringent emission limits for waste combustors prior to the development of new regulations. EPA and DOE established a multi-year Interagency Agreement (IAG) in 1991. The main objective of the IAG (and of the second IAG that was added in 1993) is to conduct a research program on thermal technologies for treating mixed waste and to establish permit procedures for these technologies particularly under the new requirements of the above-mentioned EPA Combustion Strategy. The objective of this Paper is to summarize the results of the EPA/DOE joint efforts on mixed waste treatment since the establishment of the original Interagency Agreement. Specifically, this Paper will discuss six activities that have been underway; namely: (1) National Technical Workgroup (NTW) on Mixed Waste Treatment, (2) State-of-the-Art Assessment of APC (Air Pollution Control) and Monitoring Technologies for the Rocky Flats Fluidized Bed Unit, (3) Initial Study of Permit open-quotes Roadmapclose quotes Development for Mixed Waste Treatment, (4) Risk Assessment Approach for a Mixed Waste Thermal Treatment Facility, (5) Development and Application of Technology Selection Criteria for Mixed Waste Thermal Treatment, and (6) Performance Testing of Mixed Waste Incineration: In-Situ Chlorine Capture in a Fluidized Bed Unit

  10. The Hybrid Treatment Process for treatment of mixed radioactive and hazardous wastes

    International Nuclear Information System (INIS)

    Ross, W.A.; Kindle, C.H.

    1992-04-01

    This paper describes a new process for treating mixed hazardous and radioactive waste, commonly called mixed waste. The process is called the Hybrid Treatment Process (HTP), so named because it is built on the 20 years of experience with vitrification of wastes in melters, and the 12 years of experience with treatment of wastes by the in situ vitrification (ISV) process

  11. Surgical treatment for pilon fracture of the ankle-open reduction and internal fixation.

    Science.gov (United States)

    Chen, Y W; Huang, P J; Hsu, C Y; Kuo, C H; Cheng, Y M; Lin, S Y; Chen, L H; Chiang, H C

    1998-01-01

    From 1991 to 1994, 39 ankles of 38 patients underwent surgical open reduction and internal fixation for pilon fractures. These patients included 29 males and 9 females with an average age of 38.6 y/o (range 28 y/o-58 y/o). The follow up and evaluation period averaged 31.7 months (range 22Ms-44Ms), during which time a standing x-ray for arthrosis grading and functional scale was used for clinical evaluation. Complications included 1 case of infection, 1 case of loss reduction, 2 cases of partial skin necrosis and 2 cases of delayed union. Post-traumatic arthritis occurred in 23 ankles (59%) but only 4 ankles of grade 4 arthrosis resulted in poor functional scale and the overall satisfactory rate was 82%. It was found that anatomic reduction, rigid fixation and early motion exercise are important to successful treatment of ankle fractures. Regarding pilon fracture, specifically the severity of fracture pattern and delay of reduction are important problems to overcome to ensure successful results. Therefore, adequate surgical approach for entire view of ankle joint, reduction and fixation of fibula, sufficient bone graft for articular support, intraoperative x-ray check and postoperative immobilization are essential for the achievement of better clinical results.

  12. The micro-electrolysis technique in waste water treatment

    International Nuclear Information System (INIS)

    Jiti Zhou; Weihen Yang; Fenglin Yang; Xuemin Xiang; Yulu Wang

    1997-01-01

    The micro-electrolysis is one of the efficient methods to treat some kinds of waste water. The experiments have shown its high efficiency in sewage treatment and some kinds of industrial waste water. It is suitable for pre-treatment of high concentrated waste water and deep treatment of waste water for reuse purpose. The disadvantage of micro-electrolysis is its high energy consumption in case of high electrolyte concentration. (author) 2 figs., 11 tabs., 2 refs

  13. The micro-electrolysis technique in waste water treatment

    Energy Technology Data Exchange (ETDEWEB)

    Jiti Zhou; Weihen Yang; Fenglin Yang; Xuemin Xiang; Yulu Wang [Dalian Univ. of Technology, Dalian (China)

    1997-12-31

    The micro-electrolysis is one of the efficient methods to treat some kinds of waste water. The experiments have shown its high efficiency in sewage treatment and some kinds of industrial waste water. It is suitable for pre-treatment of high concentrated waste water and deep treatment of waste water for reuse purpose. The disadvantage of micro-electrolysis is its high energy consumption in case of high electrolyte concentration. (author) 2 figs., 11 tabs., 2 refs.

  14. Treatment of mercury containing waste

    Science.gov (United States)

    Kalb, Paul D.; Melamed, Dan; Patel, Bhavesh R; Fuhrmann, Mark

    2002-01-01

    A process is provided for the treatment of mercury containing waste in a single reaction vessel which includes a) stabilizing the waste with sulfur polymer cement under an inert atmosphere to form a resulting mixture and b) encapsulating the resulting mixture by heating the mixture to form a molten product and casting the molten product as a monolithic final waste form. Additional sulfur polymer cement can be added in the encapsulation step if needed, and a stabilizing additive can be added in the process to improve the leaching properties of the waste form.

  15. Mixed waste treatment at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Larsen, M.M.; Hunt, L.F.; Sanow, D.J.

    1988-01-01

    The Idaho Operations Office of the Department of Energy (DOE) made the decision in 1984 to prohibit the disposal of mixed waste (MW) (combustible waste-toxic metal waste) in the Idaho National Engineering Laboratory (INEL) low-level radioactive waste (LLW) disposal facility. As a result of this decision and due to there being no EPA-permitted MW treatment/storage/disposal (T/S/D) facilities, the development of waste treatment methods for MW was initiated and a storage facility was established to store these wastes while awaiting development of treatment systems. This report discusses the treatment systems developed and their status. 3 refs., 2 figs., 1 tab

  16. Evaluating the technical aspects of mixed waste treatment technologies

    International Nuclear Information System (INIS)

    Bagaasen, L.M.; Scott, P.A.

    1992-10-01

    This report discusses treatment of mixed wastes which is thought to be more complicated than treatment of either hazardous or radioactive wastes. In fact, the treatment itself is no more complicated: however, the regulations that define acceptability of the final waste disposal system are significantly more entangled, and sometimes in apparent conflict. This session explores the factors that influence the choice of waste treatment technologies, and expands on some of the limitations to their application. The objective of the presentation is to describe the technical factors that influence potential treatment processes and the ramifications associated with particular selections (for example, the generation of secondary waste streams). These collectively provide a framework for making informed treatment process selections

  17. Comparison of Monolateral External Fixation and Internal Fixation for Skeletal Stabilisation in the Management of Small Tibial Bone Defects following Successful Treatment of Chronic Osteomyelitis.

    Science.gov (United States)

    Wang, Yicun; Jiang, Hui; Deng, Zhantao; Jin, Jiewen; Meng, Jia; Wang, Jun; Zhao, Jianning; Sun, Guojing; Qian, Hongbo

    2017-01-01

    To compare the salvage rate and complication between internal fixation and external fixation in patients with small bone defects caused by chronic infectious osteomyelitis debridement. 125 patients with chronic infectious osteomyelitis of tibia fracture who underwent multiple irrigation, debridement procedure, and local/systemic antibiotics were enrolled. Bone defects, which were less than 4 cm, were treated with bone grafting using either internal fixation or monolateral external fixation. 12-month follow-up was conducted with an interval of 3 months to evaluate union of bone defect. Patients who underwent monolateral external fixation had higher body mass index and fasting blood glucose, longer time since injury, and larger bone defect compared with internal fixation. No significant difference was observed in incidence of complications (23.5% versus 19.3%), surgery time (156 ± 23 minutes versus 162 ± 21 minutes), and time to union (11.1 ± 3.0 months versus 10.9 ± 3.1 months) between external fixation and internal fixation. Internal fixation had no significant influence on the occurrence of postoperation complications after multivariate adjustment when compared with external fixation. Furthermore, patients who underwent internal fixation experienced higher level of daily living scales and lower level of anxiety. It was relatively safe to use internal fixation for stabilization in osteomyelitis patients whose bone defects were less than 4 cm and infection was well controlled.

  18. Hanford facility dangerous waste permit application, 325 hazardous waste treatment units. Revision 1

    International Nuclear Information System (INIS)

    1997-07-01

    This report contains the Hanford Facility Dangerous Waste Permit Application for the 325 Hazardous Waste Treatment Units (325 HWTUs) which consist of the Shielded Analytical Laboratory, the 325 Building, and the 325 Collection/Loadout Station Tank. The 325 HWTUs receive, store, and treat dangerous waste generated by Hanford Facility programs. Routine dangerous and/or mixed waste treatment that will be conducted in the 325 HWTUs will include pH adjustment, ion exchange, carbon absorption, oxidation, reduction, waste concentration by evaporation, precipitation, filtration, solvent extraction, solids washing, phase separation, catalytic destruction, and solidification/stabilization

  19. Hanford facility dangerous waste permit application, 325 hazardous waste treatment units. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-07-01

    This report contains the Hanford Facility Dangerous Waste Permit Application for the 325 Hazardous Waste Treatment Units (325 HWTUs) which consist of the Shielded Analytical Laboratory, the 325 Building, and the 325 Collection/Loadout Station Tank. The 325 HWTUs receive, store, and treat dangerous waste generated by Hanford Facility programs. Routine dangerous and/or mixed waste treatment that will be conducted in the 325 HWTUs will include pH adjustment, ion exchange, carbon absorption, oxidation, reduction, waste concentration by evaporation, precipitation, filtration, solvent extraction, solids washing, phase separation, catalytic destruction, and solidification/stabilization.

  20. Life cycle assessment of electronic waste treatment

    International Nuclear Information System (INIS)

    Hong, Jinglan; Shi, Wenxiao; Wang, Yutao; Chen, Wei; Li, Xiangzhi

    2015-01-01

    Highlights: • Life cycle assessment of electronic waste recycling is quantified. • Key factors for reducing the overall environmental impact are indentified. • End-life disposal processes provide significant environmental benefits. • Efficiently reduce the improper disposal amount of e-waste is highly needed. • E-waste incineration can generate significant environmental burden. - Abstract: Life cycle assessment was conducted to estimate the environmental impact of electronic waste (e-waste) treatment. E-waste recycling with an end-life disposal scenario is environmentally beneficial because of the low environmental burden generated from human toxicity, terrestrial ecotoxicity, freshwater ecotoxicity, and marine ecotoxicity categories. Landfill and incineration technologies have a lower and higher environmental burden than the e-waste recycling with an end-life disposal scenario, respectively. The key factors in reducing the overall environmental impact of e-waste recycling are optimizing energy consumption efficiency, reducing wastewater and solid waste effluent, increasing proper e-waste treatment amount, avoiding e-waste disposal to landfill and incineration sites, and clearly defining the duties of all stakeholders (e.g., manufacturers, retailers, recycling companies, and consumers)

  1. Life cycle assessment of electronic waste treatment

    Energy Technology Data Exchange (ETDEWEB)

    Hong, Jinglan, E-mail: hongjing@sdu.edu.cn [Shandong Provincial Key Laboratory of Water Pollution Control and Resource Reuse, School of Environmental Science and Engineering, Shandong University, Jinan 250100 (China); Shandong University Climate Change and Health Center, Public Health School, Shandong University, Jinan 250012 (China); Shi, Wenxiao [Shandong Provincial Key Laboratory of Water Pollution Control and Resource Reuse, School of Environmental Science and Engineering, Shandong University, Jinan 250100 (China); Wang, Yutao [School of Life Science, Shandong University, Shanda South Road 27, Jinan 250100 (China); Chen, Wei [Shandong Provincial Key Laboratory of Water Pollution Control and Resource Reuse, School of Environmental Science and Engineering, Shandong University, Jinan 250100 (China); Li, Xiangzhi, E-mail: xiangzhi@sdu.edu.cn [School of Medicine, Shandong University, Jinan 250012 (China)

    2015-04-15

    Highlights: • Life cycle assessment of electronic waste recycling is quantified. • Key factors for reducing the overall environmental impact are indentified. • End-life disposal processes provide significant environmental benefits. • Efficiently reduce the improper disposal amount of e-waste is highly needed. • E-waste incineration can generate significant environmental burden. - Abstract: Life cycle assessment was conducted to estimate the environmental impact of electronic waste (e-waste) treatment. E-waste recycling with an end-life disposal scenario is environmentally beneficial because of the low environmental burden generated from human toxicity, terrestrial ecotoxicity, freshwater ecotoxicity, and marine ecotoxicity categories. Landfill and incineration technologies have a lower and higher environmental burden than the e-waste recycling with an end-life disposal scenario, respectively. The key factors in reducing the overall environmental impact of e-waste recycling are optimizing energy consumption efficiency, reducing wastewater and solid waste effluent, increasing proper e-waste treatment amount, avoiding e-waste disposal to landfill and incineration sites, and clearly defining the duties of all stakeholders (e.g., manufacturers, retailers, recycling companies, and consumers)

  2. Cosmetic arm lengthening with monorail fixator.

    Science.gov (United States)

    Agrawal, Hemendra Kumar; Singh, Balvinder; Garg, Mohit; Khatkar, Vipin; Batra, Sumit; Sharma, Vinod Kumar

    2015-01-01

    Upper limb length discrepancy is a rare occurrence. Humerus shortening may need specialized treatment to restore the functional and cosmetic status of upper limb. We report a case of humerus lengthening of 9 cm with a monorail external fixator and the result was observed during a 2-year follow-up. Humerus lengthening needs specialized focus as it is not only a cosmetic issue but also a functional demand. The monorail unilateral fixator is more functional and cosmetically acceptable, and thus becomes an effective treatment option.

  3. Waste treatment at the La Hague and Marcoule sites

    International Nuclear Information System (INIS)

    1995-04-01

    In this report, an overview of waste treatment and solidification facilities located at the La Hague and Marcoule sites, which are owned and/or operated by Cogema, provided. The La Hague facilities described in this report include the following: The STE3 liquid effluent treatment facility (in operation); the AD2 solid waste processing facility (also in operation); and the UCD alpha waste treatment facility (under construction). The Marcoule facilities described in this report, both of which are in operation, include the following: The STEL-EVA liquid effluent treatment facilities for the entire site; and the alpha waste incinerator of the UPI plant. This report is organized into four sections: this introduction, low-level waste treatment at La Hague, low-level waste treatment at Marcoule, and new process development. including the solvent pyrolysis process currently in the development stage for Cogema's plants

  4. Waste treatment at the La Hague and Marcoule sites

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-04-01

    In this report, an overview of waste treatment and solidification facilities located at the La Hague and Marcoule sites, which are owned and/or operated by Cogema, provided. The La Hague facilities described in this report include the following: The STE3 liquid effluent treatment facility (in operation); the AD2 solid waste processing facility (also in operation); and the UCD alpha waste treatment facility (under construction). The Marcoule facilities described in this report, both of which are in operation, include the following: The STEL-EVA liquid effluent treatment facilities for the entire site; and the alpha waste incinerator of the UPI plant. This report is organized into four sections: this introduction, low-level waste treatment at La Hague, low-level waste treatment at Marcoule, and new process development. including the solvent pyrolysis process currently in the development stage for Cogema`s plants.

  5. Grout treatment facility dangerous waste permit application

    International Nuclear Information System (INIS)

    1992-07-01

    The Grout Treatment Facility (GTF) will provide permanent disposal for approximately 43 Mgal of radioactive liquid waste currently being stored in underground tanks on the Hanford Site. The first step in permanent disposal is accomplished by solidifying the low-level liquid waste with cementitious dry materials. The resulting grout is cast within underground vaults. This report on the GTF contains information on the following: Hanford Site Maps, road evaluation for the grout treatment facility, Department of Ecology certificate of non-designation for centralia fly ash, double-shell tank waste compositional modeling, laboratory analysis reports for double-shell tank waste, stored in tanks 241-AN-103, 241-AN-106, and 241-AW-101, grout vault heat transfer results for M-106 grout formulation, test results for extraction procedure toxicity testing, test results for toxicity testing of double-shell tank grout, pilot-scale grout production test with a simulated low-level waste, characterization of simulated low-level waste grout produced in a pilot-scale test, description of the procedure for sampling nonaging waste storage tanks, description of laboratory procedures, grout campaign waste composition verification, variability in properties of grouted phosphate/sulfate N-reactor waste, engineering drawings, description of operating procedures, equipment list--transportable grout equipment, grout treatment facility--tank integrity assessment plan, long-term effects of waste solutions on concrete and reinforcing steel, vendor information, grout disposal facilities construction quality assurance plan, and flexible membrane liner/waste compatibility test results

  6. Nuclear Waste Treatment Program: Annual report for FY 1986

    International Nuclear Information System (INIS)

    Burkholder, H.C.; Brouns, R.A.; Powell, J.A.

    1987-09-01

    To support DOE's attainment of its goals, Nuclear Waste Treatment Program (NWTP) is to provide technology necessary for the design and operation of nuclear waste treatment facilities by commercial enterprises as part of a licensed waste management system and problem-specific treatment approaches, waste form and treatment process adaptations, equipment designs, and trouble-shooting. This annual report describes progress during FY 1986 toward meeting these two objectives. 29 refs., 59 figs., 25 tabs

  7. Nuclear Waste Treatment Program: Annual report for FY 1986

    Energy Technology Data Exchange (ETDEWEB)

    Burkholder, H.C.; Brouns, R.A. (comps.); Powell, J.A. (ed.)

    1987-09-01

    To support DOE's attainment of its goals, Nuclear Waste Treatment Program (NWTP) is to provide technology necessary for the design and operation of nuclear waste treatment facilities by commercial enterprises as part of a licensed waste management system and problem-specific treatment approaches, waste form and treatment process adaptations, equipment designs, and trouble-shooting. This annual report describes progress during FY 1986 toward meeting these two objectives. 29 refs., 59 figs., 25 tabs.

  8. Treatment of displaced talar neck fractures using delayed procedures of plate fixation through dual approaches.

    Science.gov (United States)

    Xue, Youdi; Zhang, Hui; Pei, Fuxing; Tu, Chongqi; Song, Yueming; Fang, Yue; Liu, Lei

    2014-01-01

    Treatment of talar neck fractures is challenging. Various surgical approaches and fixation methods have been documented. Clinical outcomes are often dissatisfying due to inadequate reduction and fixation with high rates of complications. Obtaining satisfactory clinical outcomes with minimum complications remains a hard task for orthopaedic surgeons. In the period from May 2007 to September 2010, a total of 31 cases with closed displaced talar neck fractures were treated surgically in our department. Injuries were classified according to the Hawkins classification modified by Canale and Kelly. Under general anaesthesia with sufficient muscle relaxation, urgent closed reduction was initiated once the patients were admitted; if the procedure failed, open reduction and provisional stabilisation with Kirschner wires through an anteromedial approach with tibiometatarsal external fixation were performed. When the soft tissue had recovered, definitive fixation was performed with plate and screws through dual approaches. The final follow-up examination included radiological analysis, clinical evaluation and functional outcomes which were carried out according to the Ankle-Hindfoot Scale of the American Orthopaedic Foot and Ankle Society (AOFAS), patient satisfaction and SF-36. Twenty-eight patients were followed up for an average of 25 months (range 18-50 months) after the injury. Only two patients had soft tissue complications, and recovery was satisfactory with conservative treatment. All of the fractures healed anatomically without malunion and nonunion, and the average union time was 14 weeks (range 12-24 weeks). Post-traumatic arthritis developed in ten cases, while six patients suffered from avascular necrosis of the talus. Secondary procedures included three cases of subtalar arthrodesis, one case of ankle arthrodesis and one case of total ankle replacement. The mean AOFAS hindfoot score was 78 (range 65-91). According to the SF-36, the average score of the

  9. Fixation of radioactive waste in glass

    International Nuclear Information System (INIS)

    Chapman, C.C.; Mendel, J.E.

    1976-08-01

    After a brief review of the source of high level wastes and the specific requirements and desirable characteristics of glass used as a storage vehicle, the development work done on two vitrification systems is outlined. One is an in-can melter system and the second is a ceramic melter. Primary emphasis has been placed on the in-can melter system for use in the near future. Both systems are capable of converting high level waste to a glass which possesses low release potential

  10. 300 Area waste acid treatment system closure plan

    International Nuclear Information System (INIS)

    LUKE, S.N.

    1999-01-01

    The Hanford Facility Dangerous Waste Permit Application is considered to be a single application organized into a General Information Portion (document number DOERL-91-28) and a Unit-Specific Portion. The scope of the Unit-Specific Portion includes closure plan documentation submitted for individual, treatment, storage, and/or disposal units undergoing closure, such as the 300 Area Waste Acid Treatment System. Documentation contained in the General Information Portion is broader in nature and could be used by multiple treatment, storage, and/or disposal units (e.g., the glossary provided in the General Information Portion). Whenever appropriate, 300 Area Waste Acid Treatment System documentation makes cross-reference to the General Information Portion, rather than duplicating text. This 300 Area Waste Acid Treatment System Closure Plan (Revision 2) includes a Hanford Facility Dangerous Waste Permit Application, Part A, Form 3. Information provided in this closure plan is current as of April 1999

  11. 300 Area waste acid treatment system closure plan

    Energy Technology Data Exchange (ETDEWEB)

    LUKE, S.N.

    1999-05-17

    The Hanford Facility Dangerous Waste Permit Application is considered to be a single application organized into a General Information Portion (document number DOERL-91-28) and a Unit-Specific Portion. The scope of the Unit-Specific Portion includes closure plan documentation submitted for individual, treatment, storage, and/or disposal units undergoing closure, such as the 300 Area Waste Acid Treatment System. Documentation contained in the General Information Portion is broader in nature and could be used by multiple treatment, storage, and/or disposal units (e.g., the glossary provided in the General Information Portion). Whenever appropriate, 300 Area Waste Acid Treatment System documentation makes cross-reference to the General Information Portion, rather than duplicating text. This 300 Area Waste Acid Treatment System Closure Plan (Revision 2) includes a Hanford Facility Dangerous Waste Permit Application, Part A, Form 3. Information provided in this closure plan is current as of April 1999.

  12. Development of new waste form for treatment and disposal of concentrated liquid radioactive waste

    International Nuclear Information System (INIS)

    Kwak, Kyung Kil; Ji, Young Yong

    2010-12-01

    The radioactive waste form should be meet the waste acceptance criteria of national regulation and disposal site specification. We carried out a characterization of rad waste form, especially the characteristics of radioactivity, mechanical and physical-chemical properties in various rad waste forms. But asphalt products is not acceptable waste form at disposal site. Thus we are change the product materials. We select the development of the new process or new materials. The asphalt process is treatment of concentrated liquid and spent-resin and that we decide the Development of new waste form for treatment and disposal of concentrated liquid radioactive waste

  13. The development of radioactive waste treatment technology(IV)

    International Nuclear Information System (INIS)

    Kim, Joon Hyung; Yim, Sung Paal; Lee, Kune Woo; Yoo, Jeong Woo; Kim, Young Min; Park, Seong Chul

    1992-03-01

    Following studies were performed in the project of development of radioactive waste treatment technology. 1) Treatment of radioactive borated liquid wastes by reverse osmosis : Separation characteristics of boric acid were estimated using cellulose acetate membrane and aromatic polyamide membrane. The performance of reverse osmosis process was evaluated in terms of boric acid recovery, radiochemical rejection, and membrane flux by operating variables such as applied pressure and feed concentration. 2) Oily waste treatment : The mathematical model to estimate oil removal efficiency is to be proposed at coalescence column. 3) Treatment of radioactive laundry waste 4) Comparison of evaporation and ion-exchange 5) State of the art of high integrity container. (Author)

  14. Percutaneous Facet Screw Fixation in the Treatment of Symptomatic Recurrent Lumbar Facet Joint Cyst: A New Technique

    Energy Technology Data Exchange (ETDEWEB)

    Amoretti, Nicolas, E-mail: amorettinicolas@yahoo.fr; Gallo, Giacomo, E-mail: giacomo.gallo83@gmail.com; Bertrand, Anne-Sophie, E-mail: asbertrand3@hotmail.com [Centre Hospitalier Universitaire de Nice (France); Bard, Robert L., E-mail: rbard@cancerscan.com [New York Medical College (United States); Kelekis, Alexis, E-mail: akelekis@med.uoa.gr [University General Hospital “ATTIKON” (Greece)

    2016-01-15

    We present a case of percutaneous treatment of symptomatic recurrent lumbar facet joint cyst resistant to all medical treatments including facet joint steroid injection. Percutaneous transfacet fixation was then performed at L4–L5 level with a cannulated screw using CT and fluoroscopy guidance. The procedure time was 30 min. Using the visual analog scale (VAS), pain decreased from 9.5, preoperatively, to 0 after the procedure. At 6-month follow-up, an asymptomatic cystic recurrence was observed, which further reduced at the 1-year follow-up. Pain remained stable (VAS at 0) during all follow-ups. CT- and fluoroscopy-guided percutaneous cyst rupture associated with facet screw fixation could be an alternative to surgery in patients suffering from a symptomatic recurrent lumbar facet joint cyst.

  15. Performance Enhancements to the Hanford Waste Treatment and Immobilization Plant Low-Activity Waste Vitrification System

    International Nuclear Information System (INIS)

    Hamel, W. F.; Gerdes, K.; Holton, L. K.; Pegg, I.L.; Bowan, B.W.

    2006-01-01

    The U.S Department of Energy Office of River Protection (DOE-ORP) is constructing a Waste Treatment and Immobilization Plant (WTP) for the treatment and vitrification of underground tank wastes stored at the Hanford Site in Washington State. The WTP comprises four major facilities: a pretreatment facility to separate the tank waste into high level waste (HLW) and low-activity waste (LAW) process streams, a HLW vitrification facility to immobilize the HLW fraction; a LAW vitrification facility to immobilize the LAW fraction, and an analytical laboratory to support the operations of all four treatment facilities. DOE has established strategic objectives to optimize the performance of the WTP facilities and the LAW and HLW waste forms to reduce the overall schedule and cost for treatment and vitrification of the Hanford tank wastes. This strategy has been implemented by establishing performance expectations in the WTP contract for the facilities and waste forms. In addition, DOE, as owner-operator of the WTP facilities, continues to evaluate 1) the design, to determine the potential for performance above the requirements specified in the WTP contract; and 2) improvements in production of the LAW and HLW waste forms. This paper reports recent progress directed at improving production of the LAW waste form. DOE's initial assessment, which is based on the work reported in this paper, is that the treatment rate of the WTP LAW vitrification facility can be increased by a factor of 2 to 4 with a combination of revised glass formulations, modest increases in melter glass operating temperatures, and a second-generation LAW melter with a larger surface area. Implementing these improvements in the LAW waste immobilization capability can benefit the LAW treatment mission by reducing the cost of waste treatment. (authors)

  16. Radiation treatment of solid wastes

    International Nuclear Information System (INIS)

    Brenner, W.; Rugg, B.; Rogers, C.

    1977-01-01

    Solid waste is now generally recognized as both a major problem and an underutilized renewable resource for materials and energy recovery. Current methods for dealing with solid wastes are admittedly inadequate for cost effective utilization of the latest material and energy values, especially of cellulose and other organics. Processes for production of energy from organic wastes including incineration, pyrolysis and biodegradation, are receiving considerable attention even though the heating value of dried organic wastes is substantially less than that of fossil fuels. An attractive alternative approach is conversion into chemical feedstocks for use as fuels, intermediates for plastics, rubbers, fibers etc., and in the preparation of foods. Radiation treatment of solid wastes offers attractive possibilities for upgrading the value of such organic waste components as cellulose and putrescible matter. The latter can be cold sterilized by radiation treatments for the production of animal feed supplements. The wide availability of cellulosic wastes warrants their consideration as an alternate feedstock to petrochemicals for fuels, intermediates and synthesis of single cell protein. The crucial step in this developing technology is optimizing the conversion of cellulose to its monomer glucose which can be accomplished by either acid or enzymatic hydrolysis. A combination pretreatment consisting of radiation of hydropulped cellulosic wastes has shown considerable promise in improving the yields of glucose for acid hydrolysis reactions at substantially lower cost than presently used methods such as grinding. Data are presented to compare the effectiveness of this pretreatment with other techniques which have been investigated. (author)

  17. 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.)

  18. Mixed and Low-Level Waste Treatment Facility Project

    International Nuclear Information System (INIS)

    1992-04-01

    Mixed and low-level wastes generated at the Idaho National Engineering Laboratory (INEL) are required to be managed according to applicable State and Federal regulations, and Department of Energy Orders that provide for the protection of human health and the environment. The Mixed and Low-Level Waste Treatment Facility Project was chartered in 1991, by the Department of Energy to provide treatment capability for these mixed and low-level waste streams. The first project task consisted of conducting engineering studies to identify the waste streams, their potential treatment strategies, and the requirements that would be imposed on the waste streams and the facilities used to process them. This report documents those studies so the project can continue with an evaluation of programmatic options, system tradeoff studies, and the conceptual design phase of the project. This report, appendix B, comprises the engineering design files for this project study. The engineering design files document each waste steam, its characteristics, and identified treatment strategies

  19. Posterior Fixation with Unilateral Same Segment Pedicle Fixation and Contralateral Hook in Surgical Treatment of Thoracolumbar Burst Fractures

    Directory of Open Access Journals (Sweden)

    Farzad Omidi-Kashani

    2016-06-01

    Full Text Available Background In surgical treatment of thoracolumbar burst fractures, most authors try to lower the number of vertebrae involved during the surgery. Objectives The aim of this study was to evaluate the outcome of a medium-segment posterior spinal fixation in these patients. Patients and Methods We retrospectively reviewed 27 patients (18 male, 9 female with mean age of 39.4 ± 15.0 years old in a before-and-after study. The mean follow-up period was 38.4 ± 15.6 months. We involved 2 intact above vertebrae and one intact below vertebra, inserting a pedicular screw at the fractured level and supplemented the construct with contralateral infralaminar hook. Clinical and radiologic characteristics were assessed with American spinal injury association (ASIA scale, oswestry disability index (ODI, visual analogue scale (VAS, and plain radiography. Data analysis was carried out by SPSS version 11.5 software. Results Mean post traumatic kyphosis was + 15.7° ± 3.3° that was changed to - 8.5° ± 4.3° and +1° ± 4.4° at immediate and last visit after surgery, respectively. Mean loss of correction (LOC was 9.5° ± 1.9° (P < 0.001. At the most recent follow-up visit, mean ODI and VAS were 15.0 ± 14.4 and 2.4 ± 2.5, respectively and 24 cases (88.9% declared excellent or good clinical results. At the last follow-up visit, LOC had no significant correlation neither with VAS nor ODI. Conclusions In surgical treatment of thoracolumbar burst fractures, a medium-segment posterior spinal fixation, although cannot maintain the radiologic reduction of the fractured vertebrae efficiently, is not only associated with acceptable clinical outcome but also spare one lower intact lumbar segment and therefore recommended.

  20. Treatment methods for radioactive mixed wastes in commercial low-level wastes: technical considerations

    International Nuclear Information System (INIS)

    MacKenzie, D.R.; Kempf, C.R.

    1986-01-01

    Treatment options for the management of three generic categories of radioactive mixed waste in commercial low-level wastes (LLW) have been identified and evaluated. These wastes were characterized as part of a BNL study in which LLW generators were surveyed for information on potential chemical hazards in their wastes. The general treatment options available for mixed wastes are destruction, immobilization, and reclamation. Solidification, absorption, incineration, acid digestion, wet-air oxidation, distillation, liquid-liquid wastes. Containment, segregation, decontamination, and solidification or containment of residues, have been considered for lead metal wastes which have themselves been contaminated and are not used for purposes of waste disposal shielding, packaging, or containment. For chromium-containing wastes, solidification, incineration, wet-air oxidation, acid digestion, and containment have been considered. For each of these wastes, the management option evaluation has included an assessment of testing appropriate to determine the effect of the option on both the radiological and potential chemical hazards present

  1. Treatment methods for radioactive mixed wastes in commercial low-level wastes: technical considerations

    Energy Technology Data Exchange (ETDEWEB)

    MacKenzie, D.R.; Kempf, C.R.

    1986-01-01

    Treatment options for the management of three generic categories of radioactive mixed waste in commercial low-level wastes (LLW) have been identified and evaluated. These wastes were characterized as part of a BNL study in which LLW generators were surveyed for information on potential chemical hazards in their wastes. The general treatment options available for mixed wastes are destruction, immobilization, and reclamation. Solidification, absorption, incineration, acid digestion, wet-air oxidation, distillation, liquid-liquid wastes. Containment, segregation, decontamination, and solidification or containment of residues, have been considered for lead metal wastes which have themselves been contaminated and are not used for purposes of waste disposal shielding, packaging, or containment. For chromium-containing wastes, solidification, incineration, wet-air oxidation, acid digestion, and containment have been considered. For each of these wastes, the management option evaluation has included an assessment of testing appropriate to determine the effect of the option on both the radiological and potential chemical hazards present.

  2. A Meta-Analysis for Postoperative Complications in Tibial Plafond Fracture: Open Reduction and Internal Fixation Versus Limited Internal Fixation Combined With External Fixator.

    Science.gov (United States)

    Wang, Dong; Xiang, Jian-Ping; Chen, Xiao-Hu; Zhu, Qing-Tang

    2015-01-01

    The treatment of tibial plafond fractures is challenging to foot and ankle surgeons. Open reduction and internal fixation and limited internal fixation combined with an external fixator are 2 of the most commonly used methods of tibial plafond fracture repair. However, conclusions regarding the superior choice remain controversial. The present meta-analysis aimed to quantitatively compare the postoperative complications between open reduction and internal fixation and limited internal fixation combined with an external fixator for tibial plafond fractures. Nine studies with 498 fractures in 494 patients were included in the present study. The meta-analysis found no significant differences in bone healing complications (risk ratio [RR] 1.17, 95% confidence interval [CI] 0.68 to 2.01, p = .58], nonunion (RR 1.09, 95% CI 0.51 to 2.36, p = .82), malunion or delayed union (RR 1.24, 95% CI 0.57 to 2.69, p = .59), superficial (RR 1.56, 95% CI 0.43 to 5.61, p = .50) and deep (RR 1.89, 95% CI 0.62 to 5.80) infections, arthritis symptoms (RR 1.20, 95% CI 0.92 to 1.58, p = .18), or chronic osteomyelitis (RR 0.31, 95% CI 0.05 to 1.84, p = .20) between the 2 groups. Copyright © 2015 American College of Foot and Ankle Surgeons. Published by Elsevier Inc. All rights reserved.

  3. The role of biotechnology on the treatment of wastes | Buyukgungor ...

    African Journals Online (AJOL)

    The role of biotechnology on the treatment of wastes. ... treatment, gas treatment and disposal of solid wastes in environmental engineering. Also ... units and biogas reactors are used extensively among the waste treatment technologies.

  4. Iliococcygeus fixation for the treatment of apical vaginal prolapse: efficacy and safety at 5 years of follow-up.

    Science.gov (United States)

    Serati, Maurizio; Braga, Andrea; Bogani, Giorgio; Leone Roberti Maggiore, Umberto; Sorice, Paola; Ghezzi, Fabio; Salvatore, Stefano

    2015-07-01

    Sacrocolpopexy is considered the gold standard treatment for vaginal vault prolapse. However, the vaginal approach is very common, with 80-90 % of procedures being performed via this route. The aim of this study was to evaluate the safety and efficacy of iliococcygeus (ICG) fixation in the treatment of vaginal vault prolapse, with a minimum follow-up of 5 years. We prospectively enrolled women with symptomatic vaginal vault prolapse (Pelvic Organ Prolapse Quantification [POP-Q] stage ≥2) who were treated with ICG fixation. Subjective success was defined in the case of Patient Global Impression of Improvement ≤ 2 and an absence of bulging symptoms. Objective success was defined as stage of prolapse < 2 in all compartments. Overall success rate was defined as women without prolapse symptoms, PGI-I ≤ 2, stage of prolapse < 2, and no need for other surgery. All women filled in the Prolapse Quality of Life (P-QOL) questionnaire both at the preoperative visit and at every follow-up visit. Multiple logistic regression was performed to identify factors involved in the risk of recurrent POP. After a median (range) follow-up of 68.8 (60-92) months the subjective, objective, and overall cure rates were 88.6 % (39 out of 44), 84.1 % (37 out of 44), and 84.1 % (37 out of 44) respectively. Only preoperative stage IV vault descensus independently predicted POP recurrence after iliococcygeus fixation (OR: 8.78 [95 % CI: 1.31-9.42]; p < 0.001). Iliococcygeus fixation is a safe and effective surgical technique for the treatment of vaginal vault prolapse with long-lasting effectiveness.

  5. Study of integral waste management systems and their effects on the environment in Thailand. Part of a coordinated programme on migration and disperios of radionuclides from storage of radioactive waste under various conditions in the terrestrial environment

    International Nuclear Information System (INIS)

    Karasuddhi, P.

    1976-02-01

    The research work carried out is divided into 3 parts: 1. Experimental study of sorption capacity of Sr-90, Cs-137 and radioactive liquid waste of OAEP onto soil and clay. 2. The fixation of radioactive sludge and resin in cement, gumcrete and bitumen. The results show that the sludge from the OAEP waste treatment plant can be fixed very well with concrete, gumcrete and bitumen, but the solidification of resin in concrete, gumcrete and bitumen is not a good method for waste treatment. In the third part, the results of environment studies around the nuclear research center are presented

  6. Emergency department external fixation for provisional treatment of pilon and unstable ankle fractures

    Directory of Open Access Journals (Sweden)

    Craig R Lareau

    2015-01-01

    Full Text Available Unstable ankle fractures and impacted tibial pilon fractures often benefit from provisional external fixation as a temporizing measure prior to definitive fixation. Benefits of external fixation include improved articular alignment, decreased articular impaction, and soft tissue rest. Uniplanar external fixator placement in the Emergency Department (ED ex-fix is a reliable and safe technique for achieving ankle reduction and stability while awaiting definitive fixation. This procedure involves placing transverse proximal tibial and calcaneal traction pins and connecting the pins with two external fixator rods. This technique is particularly useful in austere environments or when the operating room is not immediately available. Additionally, this bedside intervention prevents the patient from requiring general anesthesia and may be a cost-effective strategy for decreasing valuable operating time. The ED ex-fix is an especially valuable procedure in busy trauma centers and during mass casualty events, in which resources may be limited.

  7. New treatment centers for radioactive waste from Russian designed VVER-reactors

    International Nuclear Information System (INIS)

    Chrubasik, A.

    1997-01-01

    The nuclear power plants using Russian designed VVER-type reactors, were engineered and designed without any wastes treatment facilities. The liquid and solid waste were collected in storage tanks and shelters. After many years of operation, the storage capabilities are exhausted. The treatment of the stored and still generated waste represents a problem of reactor safety and requires a short term solution. NUKEM has been commissioned to design and construct several new treatment centers to remove and process the stored waste. This paper describes the process and lessons learned on the development of this system. The new radioactive waste treatment center (RWTC) includes comprehensive systems to treat both liquid and solid wastes. The process includes: 1) treatment of evaporator concentrates, 2) treatment of ion exchange resins, 3) treatment of solid burnable waste, 4) treatment of liquid burnable waste, 5) treatment of solid decontaminable waste, 6) treatment of solid compactible waste. To treat these waste streams, various separate systems and facilities are needed. Six major facilities are constructed including: 1. A sorting facility with systems for waste segregation. 2. A high-force compactor facility for volume reduction of non-burnable waste. 3. An incinerator facility for destruction of: 1) solid burnable waste, 2) liquid burnable waste, 3) low level radioactive ion exchange resins. 4. A facility for melting of incineration residue. 5. A cementation facility for stabilization of: 1) medium level radioactive ion exchange resins, 2) solid non compactible waste, 3) compacted solid waste. 6. Separation of radionuclides from evaporator concentrates. This presentation will address the facilities, systems, and lessons learned in the development of the new treatment centers. (author)

  8. Waste water treatment today and tomorrow

    International Nuclear Information System (INIS)

    1992-01-01

    The papers discuss waste water treatment in the legislation of the EC, the German state, the Laender and communities, as well as water protection by preventing waste production and pollutant emissions. (EF) [de

  9. Fixation distance and fixation duration to vertical road signs.

    Science.gov (United States)

    Costa, Marco; Simone, Andrea; Vignali, Valeria; Lantieri, Claudio; Palena, Nicola

    2018-05-01

    The distance of first-fixation to vertical road signs was assessed in 22 participants while driving a route of 8.34 km. Fixations to road signs were recorded by a mobile eye-movement-tracking device synchronized to GPS and kinematic data. The route included 75 road signs. First-fixation distance and fixation duration distributions were positively skewed. Median distance of first-fixation was 51 m. Median fixation duration was 137 ms with a modal value of 66 ms. First-fixation distance was linearly related to speed and fixation duration. Road signs were gazed at a much closer distance than their visibility distance. In a second study a staircase procedure was used to test the presentation-time threshold that lead to a 75% accuracy in road sign identification. The threshold was 35 ms, showing that short fixations to a road signs could lead to a correct identification. Copyright © 2018 Elsevier Ltd. All rights reserved.

  10. Regional waste treatment facilities with underground monolith disposal for all low-heat-generating nuclear wastes

    International Nuclear Information System (INIS)

    Forsberg, C.W.

    1982-01-01

    An alternative system for treatment and disposal of all ''low-heat-generating'' nuclear wastes from all sources is proposed. The system, Regional Waste Treatment Facilities with Underground Monolith Disposal (RWTF/UMD), integrates waste treatment and disposal operations into single facilities at regional sites. Untreated and/or pretreated wastes are transported from generation sites such as reactors, hospitals, and industries to regional facilities in bulk containers. Liquid wastes are also transported in bulk after being gelled for transport. The untreated and pretreated wastes are processed by incineration, crushing, and other processes at the RWTF. The processed wastes are mixed with cement. The wet concrete mixture is poured into large low-cost, manmade caverns or deep trenches. Monolith dimensions are from 15 to 25 m wide, and 20 to 60 m high and as long as required. This alternative waste system may provide higher safety margins in waste disposal at lower costs

  11. An overview of in situ waste treatment technologies

    International Nuclear Information System (INIS)

    Walker, S.; Hyde, R.A.; Piper, R.B.; Roy, M.W.

    1992-01-01

    In situ technologies are becoming an attractive remedial alternative for eliminating environmental problems. In situ treatments typically reduce risks and costs associated with retrieving, packaging, and storing or disposing-waste and are generally preferred over ex situ treatments. Each in situ technology has specific applications, and, in order to provide the most economical and practical solution to a waste problem, these applications must be understood. This paper presents an overview of thirty different in situ remedial technologies for buried wastes or contaminated soil areas. The objective of this paper is to familiarize those involved in waste remediation activities with available and emerging in situ technologies so that they may consider these options in the remediation of hazardous and/or radioactive waste sites. Several types of in situ technologies are discussed, including biological treatments, containment technologies, physical/chemical treatments, solidification/stabilization technologies, and thermal treatments. Each category of in situ technology is briefly examined in this paper. Specific treatments belonging to these categories are also reviewed. Much of the information on in situ treatment technologies in this paper was obtained directly from vendors and universities and this information has not been verified

  12. Treatment of radioactive mixed wastes in commercial low-level wastes

    International Nuclear Information System (INIS)

    Kempf, C.R.; MacKenzie, D.R.

    1985-01-01

    Management options for three generic categories of radioactive mixed waste in commercial low-level wastes have been identified and evaluated. These wastes were characterized as part of a BNL study in which a large number of generators were surveyed for information on potentially hazardous low-level wastes. The general management targets adopted for mixed wastes are immobilization, destruction, and reclamation. It is possible that these targets may not be practical for some wastes, and for these, goals of stabilization or reduction of hazard are addressed. Solidification, absorption, incineration, acid digestion, segregation, and substitution have been considered for organic liquid wastes. Containment, segregation, and decontamination and re-use have been considered for lead metal wastes which have themselves been contaminated and are not used for purposes of waste disposal shielding, packaging, or containment. For chromium-containing wastes, solidification, incineration, containment, substitution, chemical reduction, and biological removal have been considered. For each of these wastes, the management option evaluation has necessarily included assessment/estimation of the effect of the treatment on both the radiological and potential chemical hazards present. 10 refs

  13. Nuclear waste treatment program: Annual report for FY 1987

    International Nuclear Information System (INIS)

    Brouns, R.A.; Powell, J.A.

    1988-09-01

    Two of the US Department of Energy's (DOE) nuclear waste management-related goals are to ensure that waste management is not an obstacle to the further development of light-water reactors and the closure of the nuclear fuel cycle and to fulfill its institutional responsibility for providing safe storage and disposal of existing and future nuclear wastes. As part of its approach to achieving these goals, the Office of Remedial Action and Waste Technology of DOE established what is now called the Nuclear Waste Treatment Program (NWTP) at the Pacific Northwest Laboratory during the second half of FY 1982. To support DOE's attainment of its goals, the NWTP is to provide technology necessary for the design and operation of nuclear waste treatment facilities by commercial enterprises as part of a licensed waste management system and problem-specific treatment approaches, waste form and treatment process adaptations, equipment designs, and trouble-shooting assistance, as required to treat existing wastes. This annual report describes progress during FY 1987 towards meeting these two objectives. 24 refs., 59 figs., 24 tabs

  14. Methods for the Evaluation of Waste Treatment Processes

    Directory of Open Access Journals (Sweden)

    Hans-Joachim Gehrmann

    2017-01-01

    Full Text Available Decision makers for waste management are confronted with the problem of selecting the most economic, environmental, and socially acceptable waste treatment process. This paper elucidates evaluation methods for waste treatment processes for the comparison of ecological and economic aspects such as material flow analysis, statistical entropy analysis, energetic and exergetic assessment, cumulative energy demand, and life cycle assessment. The work is based on the VDI guideline 3925. A comparison of two thermal waste treatment plants with different process designs and energy recovery systems was performed with the described evaluation methods. The results are mainly influenced by the type of energy recovery, where the waste-to-energy plant providing district heat and process steam emerged to be beneficial in most aspects. Material recovery options from waste incineration were evaluated according to sustainability targets, such as saving of resources and environmental protection.

  15. SOLAR ENERGY APPLICATION IN WASTE TREATMENT- A REVIEW

    African Journals Online (AJOL)

    This review is an exposure on the various ways that solar energy can be harnessed for numerous waste treatment processes. Almost all forms of waste treatment require energy which is scarcely available considering the global energy crisis. The objective of this study is to enumerate the solar energy applications in waste ...

  16. 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

  17. Future-proof radioactive waste treatment technologies for nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Buettner, Klaus; Braehler, Georg [NUKEM Technologies Engineering Services GmbH, Alzenau (Germany)

    2014-08-15

    In order to select the optimal treatment method for radioactive waste three options can be considered. First, to treat the radioactive waste only to allow long term interim storage until the waste acceptance criteria are defined and the disposal sites are operable. Second, to select treatment methods just in compliance with the current state of discussion with the regard to the above. Third, taking also the future development in the field of waste acceptance criteria and disposal into account. When developing waste treatment systems for Nuclear Power Plants NUKEM Technologies follows the following targets, minimisation of the amount of radioactive waste, maximisation of free release material, volume reduction, avoidance of unwanted materials in the waste package, as well as efficient waste treatment solutions (low investment, high volume reduction). With its technologies produced waste packages fulfil the most stringent waste acceptance criteria.

  18. Commercial waste treatment R and D needs in the United States

    International Nuclear Information System (INIS)

    Burkholder, H.C.

    1982-05-01

    The mission of the commercial waste treatment program is to establish treatment technology for safe and efficient management of high-level and transuranic wastes from reprocessing and fuel fabrication and special wastes from other fuel cycle activities. The four functional objectives that must be achieved to fulfill the mission are: (1) define waste product and treatment process performance requirements; (2) specify adequately safe waste products and verify their performance; (3) specify adequately efficient treatment processes and equipment and verify their performance; (4) solve existing waste treatment problems using verified products and processes. Although commercial waste treatment technology is in many respects highly advanced, there remains a number of areas where significant research and development is needed. These are: (1) technically-based performance requirements for both waste products and treatment processes; (2) pilot-scale radioactive demonstration of liquid-fed ceramic melting process and equipment for borosilicate glass; (3) non-glass TRU waste product and treatment process development; (4) waste product performance testing and predictive modeling; (5) quality verification for treatment processes

  19. Temperature development and sterilization of red pine poles during CCA treatment, elevated temperature fixation and drying

    Energy Technology Data Exchange (ETDEWEB)

    Cooper, P.; Albright, M.; Srinivasan, U.; Ung, A. [New Brunswick Univ., Fredericton, NB (Canada). Wood Science and Technology Centre

    2002-07-01

    The application of chromated copper arsenate (CCA) treatment and fixation and drying under the conditions of the study to large red pine poles left for an air seasoning period of 10 months in Quebec, Canada progressively reduced the number of micro-organisms present. A large number of microfungi isolations were effected before the treatment from the sapwood and heartwood of all poles and wood decay fungi on 8 selected poles from the 20 test poles. They originated from the sapwood zone. A reduction of approximately 50 per cent in the number of microfungi isolated from the sapwood was noted after the CCA treatment. In the case of 9 of 30 poles, basidiomycetes were isolated after treatment primarily from the untreated heartwood. There were a few instances where basidiomycetes were isolated from unpenetrated sapwood (wet pockets). Temperatures of 55 to 60 degrees Celsius were achieved under moderate temperature fixation schedules (20 hours) for approximately 5 hours at full sapwood depth. Only by the end of the schedule was a temperature of 55 degrees celsius achieved at the centre of the poles. Most of the microfungi were eliminated by this temperature regime. Trichoderma was eliminated, and only one isolation of basidiomycetes was left from the heartwood of one pole. Temperatures of 55 to 60 degrees Celsius were achieved in the wood core for 9 to 10 days during kiln drying. No basidiomycete isolations remained after this exposure. In several of the poles, there was evidence of Paecilomyces variotii, a thermo-tolerant species and a number of species of Penicillium moulds. It was concluded that there was a negligible probability of decay fungi surviving the sequence of processes as described, given the effectiveness of the fixation exposure and the higher wood temperatures sustained for longer periods. 16 refs., 5 tabs., 2 figs.

  20. Assessing mixed waste treatment technologies

    International Nuclear Information System (INIS)

    Berry, J.B.; Bloom, G.A.; Hart, P.W.

    1994-01-01

    The US Department of Energy (DOE) is responsible for the management and treatment of its mixed low-level wastes (MLLW). As discussed earlier in this conference MLLW are regulated under both the Resource Conservation and Recovery Act and various DOE orders. During the next 5 years, DOE will manage over 1,200,000 m 3 of MLLW and mixed transuranic (MTRU) waste at 50 sites in 22 states (see Table 1). The difference between MLLW and MTRU waste is in the concentration of elements that have a higher atomic weight than uranium. Nearly all of this waste will be located at 13 sites. More than 1400 individual mixed waste streams exist with different chemical and physical matrices containing a wide range of both hazardous and radioactive contaminants. Their containment and packaging vary widely (e.g., drums, bins, boxes, and buried waste). This heterogeneity in both packaging and waste stream constituents makes characterization difficult, which results in costly sampling and analytical procedures and increased risk to workers

  1. A novel combined method of osteosynthesis in treatment of tibial fractures: a comparative study on sheep with application of rod-through-plate fixator and bone plating.

    Science.gov (United States)

    Tralman, G; Andrianov, V; Arend, A; Männik, P; Kibur, R T; Nõupuu, K; Uksov, D; Aunapuu, M

    2013-04-01

    The study compares the efficiency of a new bone fixator combining periostal and intramedullary osteosynthesis to bone plating in treatment of tibial fractures in sheep. Experimental osteotomies were performed in the middle third of the left tibia. Animals were divided into two groups: in one group (four animals) combined osteosynthesis (rod-through-plate fixator, RTP fixator) was applied, and in the other group (three animals) bone plating was used. The experiments lasted for 10 weeks during which fracture union was followed by radiography, and the healing process was studied by blood serum markers reflecting bone turnover and by histological and immunohistochemical investigations. In the RTP fixator group, animals started to load body weight on the operated limbs the next day after the surgery, while in the bone plating group, this happened only on the seventh day. In the RTP fixator group, consolidation of fractures was also faster, as demonstrated by radiographical, histological, and immunohistochemical investigations and in part by blood serum markers for bone formation. It can be concluded that application of RTP fixation is more efficient than plate fixation in the treatment of experimental osteotomies of long bones in sheep. © 2012 Blackwell Verlag GmbH.

  2. Treatment of ORNL liquid low-level waste

    International Nuclear Information System (INIS)

    Berry, J.B.; Brown, C.H. Jr.; Fowler, V.L.; Robinson, S.M.

    1988-01-01

    Discontinuation of the hydrofracture disposal method at Oak Ridge National Laboratory (ORNL) has caused intensive efforts to reduce liquid waste generation. Improving the treatment of slightly radioactive liquid waste, called process waste, has reduced the volume of the resulting contaminated liquid radioactive waste effluent by 66%. Proposed processing improvements could eliminate the contaminated liquid effluent and reduce solid low-level waste by an additional one-third. The improved process meets stringent discharge limits for radionuclides. Discharge limits for radionuclides are expected to be enforced at the outfall of the treatment plant to a creek; currently, limits are enforced at the reservation boundary. Plant discharge is monitored according to the National Pollutant Discharge Elimination System (NPDES) permit for ORNL. 1 ref., 4 figs., 2 tabs

  3. Treatment methods for radioactive mixed wastes in commercial low-level wastes - technical considerations

    International Nuclear Information System (INIS)

    MacKenzie, D.R.; Kempf, C.R.

    1986-01-01

    Treatment options for the management of three generic categories of radioactive mixed waste in commercial low-level wastes (LLW) have been identified and evaluated. These wastes were characterized as part of a BNL study in which LLW generators were surveyed for information on potential chemical hazards in their wastes. The general treatment options available for mixed wastes are destruction, immobilization, and reclamation. Solidification, absorption, incineration, acid digestion, wet-air oxidation, distillation, liquid-liquid solvent extraction, and specific chemical destruction techniques have been considered for organic liquid wastes. Containment, segregation, decontamination, and solidification or containment of residues, have been considered for lead metal wastes which have themselves been contaminated and are not used for purposes of waste disposal shielding, packaging, or containment. For chromium-containing wastes, solidification, incineration, wet-air oxidation, acid digestion, and containment have been considered. Fore each of these wastes, the management option evaluation has included an assessment of testing appropriate to determine the effect of the option on both the radiological and potential chemical hazards present

  4. USDOE activities in low-level radioactive waste treatment

    International Nuclear Information System (INIS)

    Vath, J.E.

    1981-01-01

    This paper describes current research, development and demonstration (R, D and D) programs sponsored by the US Department of Energy in the area of low-level radioactive waste treatment. During the twelve month period ending September 30, 1981, 14 prime US Department of Energy contractors were involved with over 40 low-level radioactive waste disposal technology projects. Three specific projects or task areas have been selected for discussion to illustrate new and evolving technologies, and application of technology developed in other waste management areas to low-level waste treatment. The areas to be discussed include a microwave plasma torch incinerator, application of waste vitrification, and decontamination of metal waste by melting

  5. [Results of femoral lengthening over an intramedullary nail and external fixator].

    Science.gov (United States)

    Jasiewicz, Barbara; Kacki, Wojciech; Tesiorowski, Maciej; Potaczek, Tomasz

    2008-01-01

    Current techniques of operative limb lengthening usually are based on distraction osteogenesis. One of the techniques is limb lengthening over an intramedullary nail. The goal of this study is to evaluate the results of femoral lengthening over an intramedullary nail. Between 1999 and 200619 femoral "over nail" lengthenings were performed. There were 7 males and 12 females. Mean patients' age at surgery was 15.8 years, and mean initial femoral shortening was 5.1 cm. Operative technique consisted of one-stage implantation of intramedullary nail and external fixator. Ilizarov apparatus was used in 9 patients, monolateral fixator in 10 cases--ORTHOFIX in 9 patients, Wagner fixator--in 1 patient. Intramedullary nail was locked proximally with screws or Schanz pins from external fixator. After distraction phase, external fixator was removed and distal locking screws were applied. Evaluation criteria: obtained lengthening, time of external fixator, treatment time, healing index, external fixation index, range of motion in hip and knee joints and complications according to Paley. The mean lengthening was 4.6 cm, and mean distraction time was 66.6 days. Mean time of external fixation was 115.5 days, and external fixation index was 26.2 days for centimeter. Healing index was 36.9 days for centimeter. In cases with monolateral fixator, healing index did not differ with the whole group. During treatment 18 complications occurred, for a rate of 0.9 complication per segment. Lengthening over an intramedullary nail reduces the time of external fixator. Over nail femoral lengthening can prevent axis deviation following regenerate bending. Complication rate is similar to lengthenings with the classic Ilizarov technique. There are no differences in the treatment time in relation to the type of external fixator.

  6. Radionuclide fixation mechanisms in rocks

    International Nuclear Information System (INIS)

    Nakashima, S.

    1991-01-01

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

  7. Commercial waste treatment program annual progress report for FY 1983

    Energy Technology Data Exchange (ETDEWEB)

    McElroy, J.L.; Burkholder, H.C. (comps.)

    1984-02-01

    This annual report describes progress during FY 1983 relating to technologies under development by the Commercial Waste Treatment Program, including: development of glass waste form and vitrification equipment for high-level wastes (HLW); waste form development and process selection for transuranic (TRU) wastes; pilot-scale operation of a radioactive liquid-fed ceramic melter (LFCM) system for verifying the reliability of the reference HLW treatment proces technology; evaluation of treatment requirements for spent fuel as a waste form; second-generation waste form development for HLW; and vitrification process control and product quality assurance technologies.

  8. Treatment of radioactive organics liquid wastes

    International Nuclear Information System (INIS)

    Morales Galarce, Tania

    1999-01-01

    Because of the danger that radioactive wastes can pose to society and to the environment a viable treatment alternative must be developed to prepare these wastes for final disposal. The waste studied in this work is a liquid organic waste contaminated with the radioisotope tritium. This must be treated and then changed into solid form in a 200 liter container. This study defined an optimum formulation that immobilizes the liquid waste. The organic waste is first submitted to an absorption treatment, with Celite absorbent, which had the best physical characteristics from the point of view of radioactive waste management. Then this was solidified by forming a cement mortar, using a highly resistant local cement, Polpaico 400. Various mixes were tested, with different water/cement, waste/absorbent and absorbed waste/cement ratios, until a mixture that met the quality control requirements was achieved. The optimum mixture obtained has a water/cement ratio of 0.35 (p/p) that is the amount of water needed to make the mixture workable, and minimum water for hydrating the cement; a waste/absorbent ration of 0.5 (v/v), where the organic liquid is totally absorbed, and is incorporated in the solid's crystalline network; and an absorbed waste/cement ratio of 0.8 (p/p), which represents the minimum amount of cement needed to obtain a solid product with the required mechanical resistance. The mixture's components join together with no problem, to produce a good workable mixture. It takes about 10 hours for the mixture to harden. After 14 days, the resulting solid product has a resistance to compression of 52 Kgf/cm2. The formulation contains 22.9% immobilized organic waste, 46.5% cement, 14.3% Celite and 16.3% water. Organic liquid waste can be treated and a solid product obtained, that meets the qualitative and quantitative parameters required for its disposal. (CW)

  9. STUDY ON WASTE WATER TREATMENT PLANTS

    Directory of Open Access Journals (Sweden)

    Mariana DUMITRU

    2015-04-01

    Full Text Available Biogas is more and more used as an alternative source of energy, considering the fact that it is obtained from waste materials and it can be easily used in cities and rural communities for many uses, between which, as a fuel for households. Biogas has many energy utilisations, depending on the nature of the biogas source and the local demand. Generally, biogas can be used for heat production by direct combustion, electricity production by fuel cells or micro-turbines, Combined Hest and Power generation or as vehicle fuel. In this paper we search for another uses of biogas and Anaerobe Digestion substrate, such as: waste water treatment plants and agricultural wastewater treatment, which are very important in urban and rural communities, solid waste treatment plants, industrial biogas plants, landfill gas recovery plants. These uses of biogas are very important, because the gas emissions and leaching to ground water from landfill sites are serious threats for the environment, which increase more and more bigger during the constant growth of some human communities. That is why, in the developed European countries, the sewage sludge is treated by anaerobe digestion, depending on national laws. In Romania, in the last years more efforts were destined to use anaerobe digestion for treating waste waters and management of waste in general. This paper can be placed in this trend of searching new ways of using with maximum efficiency the waste resulted in big communities.

  10. Radiological, physical, and chemical characterization of additional alpha contaminated and mixed low-level waste for treatment at the advanced mixed waste treatment project

    International Nuclear Information System (INIS)

    Hutchinson, D.P.

    1995-07-01

    This document provides physical, chemical, and radiological descriptive information for a portion of mixed waste that is potentially available for private sector treatment. The format and contents are designed to provide treatment vendors with preliminary information on the characteristics and properties for additional candidate portions of the Idaho National Engineering Laboratory (INEL) and offsite mixed wastes not covered in the two previous characterization reports for the INEL-stored low-level alpha-contaminated and transuranic wastes. This report defines the waste, provides background information, briefly reviews the requirements of the Federal Facility Compliance Act (P.L. 102-386), and relates the Site Treatment Plans developed under the Federal Facility Compliance Act to the waste streams described herein. Each waste is summarized in a Waste Profile Sheet with text, charts, and tables of waste descriptive information for a particular waste stream. A discussion of the availability and uncertainty of data for these waste streams precedes the characterization descriptions

  11. Radiological, physical, and chemical characterization of additional alpha contaminated and mixed low-level waste for treatment at the advanced mixed waste treatment project

    Energy Technology Data Exchange (ETDEWEB)

    Hutchinson, D.P.

    1995-07-01

    This document provides physical, chemical, and radiological descriptive information for a portion of mixed waste that is potentially available for private sector treatment. The format and contents are designed to provide treatment vendors with preliminary information on the characteristics and properties for additional candidate portions of the Idaho National Engineering Laboratory (INEL) and offsite mixed wastes not covered in the two previous characterization reports for the INEL-stored low-level alpha-contaminated and transuranic wastes. This report defines the waste, provides background information, briefly reviews the requirements of the Federal Facility Compliance Act (P.L. 102-386), and relates the Site Treatment Plans developed under the Federal Facility Compliance Act to the waste streams described herein. Each waste is summarized in a Waste Profile Sheet with text, charts, and tables of waste descriptive information for a particular waste stream. A discussion of the availability and uncertainty of data for these waste streams precedes the characterization descriptions.

  12. Developing a dependable approach for evaluating waste treatment data

    International Nuclear Information System (INIS)

    Gering, K.L.

    1997-01-01

    Decision makers involved with hazardous waste treatment issues are faced with the challenge of making objective evaluations concerning treatment formulations. This work utilizes an effectiveness factor (denoted as η) as the basis for waste treatment evaluations, which was recently developed for application to mixed waste treatability studies involving solidification and stabilization at the Idaho National Engineering and Environmental Laboratory. The effectiveness factor incorporates an arbitrary treatment criterion Φ, which in practice could be the Toxicity Characteristic Leaching Procedure, Unconfined Compressive Strength, Leachability Index, or any other criterion used to judge treatment performance. Three values for Φ are utilized when assessing a given treatment formulation: before treatment, after treatment, and a reference value (typically a treatment standard). The expression for η also incorporates the waste loading as the prime experimental parameter, and accounts for the contribution that each hazard has upon the overall treatment performance. Also discussed are general guidelines for numerical boundaries and statistical interpretations of treatment data. Case studies are presented that demonstrate the usefulness of the effectiveness factor and related numerical methods, where the typical hazards encountered are toxic metals within mixed waste

  13. 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.

  14. Hanford Site waste treatment/storage/disposal integration

    International Nuclear Information System (INIS)

    MCDONALD, K.M.

    1999-01-01

    In 1998 Waste Management Federal Services of Hanford, Inc. began the integration of all low-level waste, mixed waste, and TRU waste-generating activities across the Hanford site. With seven contractors, dozens of generating units, and hundreds of waste streams, integration was necessary to provide acute waste forecasting and planning for future treatment activities. This integration effort provides disposition maps that account for waste from generation, through processing, treatment and final waste disposal. The integration effort covers generating facilities from the present through the life-cycle, including transition and deactivation. The effort is patterned after the very successful DOE Complex EM Integration effort. Although still in the preliminary stages, the comprehensive onsite integration effort has already reaped benefits. These include identifying significant waste streams that had not been forecast, identifying opportunities for consolidating activities and services to accelerate schedule or save money; and identifying waste streams which currently have no path forward in the planning baseline. Consolidation/integration of planned activities may also provide opportunities for pollution prevention and/or avoidance of secondary waste generation. A workshop was held to review the waste disposition maps, and to identify opportunities with potential cost or schedule savings. Another workshop may be held to follow up on some of the long-term integration opportunities. A change to the Hanford waste forecast data call would help to align the Solid Waste Forecast with the new disposition maps

  15. Mixed Waste Treatment Project: Computer simulations of integrated flowsheets

    International Nuclear Information System (INIS)

    Dietsche, L.J.

    1993-12-01

    The disposal of mixed waste, that is waste containing both hazardous and radioactive components, is a challenging waste management problem of particular concern to DOE sites throughout the United States. Traditional technologies used for the destruction of hazardous wastes need to be re-evaluated for their ability to handle mixed wastes, and in some cases new technologies need to be developed. The Mixed Waste Treatment Project (MWTP) was set up by DOE's Waste Operations Program (EM30) to provide guidance on mixed waste treatment options. One of MWTP's charters is to develop flowsheets for prototype integrated mixed waste treatment facilities which can serve as models for sites developing their own treatment strategies. Evaluation of these flowsheets is being facilitated through the use of computer modelling. The objective of the flowsheet simulations is to provide mass and energy balances, product compositions, and equipment sizing (leading to cost) information. The modelled flowsheets need to be easily modified to examine how alternative technologies and varying feed streams effect the overall integrated process. One such commercially available simulation program is ASPEN PLUS. This report contains details of the Aspen Plus program

  16. Treatment of unstable fractures, dislocations and fracture-dislocations of the cervical spine with Senegas plate fixation

    NARCIS (Netherlands)

    Moerman, J.; Harth, A.; Trimpont, van I.; Uyttendaele, D.; Verdonk, R.; Claessens, H.A.; Verbeke, S.

    1994-01-01

    The results of the anterior approach to the cervical spine for the treatment of fractures and dislocations by arthrodesis and Senegas plate fixation are described. Twenty-two patients underwent a one- or two-level arthrodesis of the cervical spine. Their mean age was 42 years. The injuries were

  17. Chemical treatment of mixed waste can be done.....Today exclamation point

    International Nuclear Information System (INIS)

    Honigford, L.; Dilday, D.; Cook, D.; Sattler, J.

    1996-01-01

    The Chemical Treatment Project is one in a series of projects implemented by the FEMP to treat mixed waste. The projects were initiated to address concerns regarding treatment capacity for mixed waste and to comply with requirements established by the Federal Facility Compliance Act. The Chemical Treatment Project is designed to utilize commercially available mobile technologies to perform treatment at the FEMP site. The waste in the Project consists of a variety of waste types with a wide range of hazards and physical characteristics. The treatment processes to be established for the waste types will be developed by a systematic approach including waste streams evaluation, projectization of the waste streams, and categorization of the stream. This information is utilized to determine the proper train of treatment which will be required to lead the waste to its final destination (i.e., disposal). This approach allows flexibility to manage a wide variety of waste in a cheaper, faster manner than designing a single treatment technology diverse enough to manage all the waste streams

  18. Treatment and immobilization of intermediate-level radioactive wastes

    International Nuclear Information System (INIS)

    Lerch, R.E.; Greenhalgh, W.O.; Partridge, J.A.; Richardson, G.L.

    1979-01-01

    A new program underway at the Hanford Engineering Development Laboratory (HEDL) to develop and demonstrate treatment and immobilization technologies for intermediate-level wastes (ILW) generated in the nuclear fuel cycle is discussed. ILW are defined as those liquid and solid radioactive wastes, other than high-level wastes and fuel cladding hulls, that in packaged form have radiation dose readings greater than 200 millirem/hr at the packaged surface and 10 millirem/hr at three feet from the surface. The IAEA value of 10 4 Ci/m 3 for ILW defines the upper limit. For comparative purposes, reference is also made to certain aspects of low-level radioactive wastes (LLW). Initial work has defined the sources, quantities and types of wastes which comprise ILW. Because of the wide differences in composition (e.g., acids, salt solutions, resins and zeolites, HEPA filters, etc.) the wastes may require different treatments, particularly those wastes containing volatile contaminants. The various types of ILW have been grouped into categories amenable to similar treatment. Laboratory studies are underway to define treatment technologies for liquid ILW which contain volatile contaminants and to define immobilization parameters for the residues resulting from treatment of ILW. Immobilization agents initially being evaluated for the various residues include cement, urea-formaldehyde, and bitumen although other immobilization agents will be studied. The program also includes development of acceptable test procedures for the final immobilized products as well as development of proposed criteria for storage, transportation, and disposal of the immobilized ILW

  19. Managing AVN following internal fixation: treatment options and clinical results.

    Science.gov (United States)

    Hoskinson, Simon; Morison, Zachary; Shahrokhi, Shahram; Schemitsch, Emil H

    2015-03-01

    Avascular necrosis (AVN) after internal fixation of intracapsular hip fractures is a progressive multifactorial disease that ultimately results in local ischemia with ensuing osteocyte necrosis and structural compromise. This disease can cause significant clinical morbidity and affects patients of any age, including young and active patients. Effective treatment of this condition among young adults is challenging due to their high functional demands. The aim of managing AVN is to relieve pain, preserve range of movement and improve function. Treatment methods vary depending on the stage of the disease and can be broadly categorised into two options, hip preserving surgery and hip arthroplasty. Although, hip preserving techniques are attractive in the young adult, they may alter the morphology of the proximal femur and make subsequent arthroplasty more challenging. Conversely, arthroplasty in the young adult may require repeat revision procedures throughout the patient's life. Current evidence suggests that modifications of prevailing treatments, in addition to new technologies, have led to the development of management strategies that may be able to alter the course of femoral head osteonecrosis. This review aims to summarise the options available for treatment of AVN in the young adult and review the clinical results. Copyright © 2014 Elsevier Ltd. All rights reserved.

  20. Process evaluation for treatment of aluminium bearing declad waste

    International Nuclear Information System (INIS)

    Banerjee, D.; Rao, Manjula A.; Srinivas, C.; Wattal, P.K.

    2012-01-01

    Declad waste generated by the process of chemical decladding of Al-cladded uranium metal fuel is characterized by highly alkaline, high Al bearing intermediate level waste. It was found that the process developed and adopted in India for plant scale treatment of alkaline intermediate level waste (ILW) is unsuitable for treatment of declad waste. This is mainly due to its exotic characteristics, notably substantial amounts of aluminium in the declad waste. As part of development of treatment scheme for this waste, 137 Cs removal by RFPR has been demonstrated earlier and the present paper reports the results of further processing of the Cs-lean effluent. The waste simulated with respect to the major chemical constituents of stored Al-bearing alkaline ILW after 137 Cs and 90 Sr removal by ion exchange, is used in this study

  1. Plasma technology for waste treatment

    International Nuclear Information System (INIS)

    Cohn, D.R.

    1995-01-01

    Improved environmental cleanup technology is needed to meet demanding goals for remediation and treatment of future waste streams. Plasma technology has unique features which could provide advantages of reduced secondary waste, lower cost, and onsite treatment for a wide variety of applications. Plasma technology can provide highly controllable processing without the need for combustion heating. It can be used to provide high temperature processing (∼10,000 degrees C). Plasma technology can also be employed for low temperature processing (down to room temperature range) through selective plasma chemistry. A graphite electrode arc plasma furnace at MIT has been used to investigate high temperature processing of simulated solid waste for Department of Energy environmental cleanup applications. Stable, non-leachable glass has been produced. To ensure reliable operation and to meet environmental objectives, new process diagnostics have been developed to measure furnace temperature and to determine metals emissions in the gaseous effluent. Selective plasma destruction of dilute concentrations of hazardous compounds in gaseous waste streams has been investigated using electron beam generated plasmas. Selective destruction makes it possible to treat the gas steam at relatively low temperatures in the 30-300 degrees C range. On-line infrared measurements have been used in feedback operation to maximize efficiency and ensure desired performance. Plasma technology and associated process diagnostics will be used in future studies of a wide range of waste streams

  2. Method and techniques of radioactive waste treatment

    International Nuclear Information System (INIS)

    Ghafar, M.; Aasi, N.

    2002-04-01

    This study illustrates the characterization of radioactive wastes produced by the application of radioisotopes in industry and research. The treatment methods of such radioactive wastes, chemical co-precipitation and ion exchange depending on the technical state of radioactive waste management facility in Syria were described. The disposal of conditioned radioactive wastes, in a safe way, has been discussed including the disposal of the radioactive sources. The characterizations of the repository to stock conditioned radioactive wastes were mentioned. (author)

  3. Life cycle assessment of advanced waste water treatment

    DEFF Research Database (Denmark)

    Larsen, Henrik Fred; Hansen, Peter Augusto

    The EU FP6 NEPTUNE project is related to the EU Water Framework Directive and the main goal is to develop new and optimize existing waste water treatment technologies (WWTT) and sludge handling methods for municipal waste water. Besides nutrients, a special focus area is micropollutants (e....... In total more that 20 different waste water and sludge treatment technologies are to be assessed. This paper will present the preliminary LCA results from running the induced versus avoided impact approach (mainly based on existing LCIA methodology) on one of the advanced treatment technologies, i...

  4. Treatment needs for greater-than-Class C low-level wastes

    International Nuclear Information System (INIS)

    Ross, W.A.; Brouns, R.A.; Burkholder, H.C.

    1988-01-01

    Greater-than-Class C (GTCC) radioactive wastes are those low-level wastes that exceed the 10CFR61 limits for shallow-land burial but are not within the historical definition of high-level wastes (i.e., spent fuel and first-cycle reprocessing wastes). The GTCC category can include all transuranic (TRU) wastes, although for the purposes of this paper, contact-handled defense TRU wastes are excluded because of the major efforts in the past decade to prepare them for disposal at the Waste Isolation Pilot Plant (WIPP). Thus, the GTCC category includes all high-activity and remote-handled TRU wastes regardless of origin. This paper defines the need for treatment of existing and projected GTCC low-level radioactive wastes in the United States. The sources, characteristics, treatment considerations, and methods for treatment are reviewed

  5. Technology for safe treatment of radioisotope organic wastes

    Energy Technology Data Exchange (ETDEWEB)

    Oh, Won Jin; Park, Chong Mook; Choi, W. K.; Lee, K. W.; Moon, J. K.; Yang, H. Y.; Kim, B. T.; Park, S. C

    1999-12-01

    An examination of chemical and radiological characteristics of RI organic liquid waste, wet oxidation by Fenton reaction and decomposition liquid waste treatment process were studied. These items will be applied to develop the equipment of wet oxidation and decomposition liquid waste treatment mixed processes for the safe treatment of RI organic liquid waste which is consisted of organic solvents such as toluene, alcohol and acetone. Two types of toluene solutions were selected as a candidate decomposition material. As for the first type, the concentration of toluene was above 20 vol percent. As for the second type, the solubility of toluene was considered. The decomposition ration by Fenton reaction was above 95 percent for both of them. From the adsorption equilibrium tests, a -Na{sup +} substituted/acid treated activated carbon and Zeocarbon mixed adsorbent was selected for the fixed adsorption column. This mixed adsorbent will be used to obtain the basic design data of liquid waste purification equipment for the treatment of decomposition liquid waste arising from the wet oxidation process. Solidification and degree of strength tests were performed with the simulated sludge/spent adsorbent of MgO as an oxide type and KH{sub 2}PO{sub 4}. From the test results, the design and fabrication of wet oxidation and liquid waste purification process equipment was made, and a performance test was carried out. (author)

  6. Technology for safe treatment of radioisotope organic wastes

    International Nuclear Information System (INIS)

    Oh, Won Jin; Park, Chong Mook; Choi, W. K.; Lee, K. W.; Moon, J. K.; Yang, H. Y.; Kim, B. T.; Park, S. C.

    1999-12-01

    An examination of chemical and radiological characteristics of RI organic liquid waste, wet oxidation by Fenton reaction and decomposition liquid waste treatment process were studied. These items will be applied to develop the equipment of wet oxidation and decomposition liquid waste treatment mixed processes for the safe treatment of RI organic liquid waste which is consisted of organic solvents such as toluene, alcohol and acetone. Two types of toluene solutions were selected as a candidate decomposition material. As for the first type, the concentration of toluene was above 20 vol percent. As for the second type, the solubility of toluene was considered. The decomposition ration by Fenton reaction was above 95 percent for both of them. From the adsorption equilibrium tests, a -Na + substituted/acid treated activated carbon and Zeocarbon mixed adsorbent was selected for the fixed adsorption column. This mixed adsorbent will be used to obtain the basic design data of liquid waste purification equipment for the treatment of decomposition liquid waste arising from the wet oxidation process. Solidification and degree of strength tests were performed with the simulated sludge/spent adsorbent of MgO as an oxide type and KH 2 PO 4 . From the test results, the design and fabrication of wet oxidation and liquid waste purification process equipment was made, and a performance test was carried out. (author)

  7. Preliminary analysis of treatment strategies for transuranic wastes from reprocessing plants

    International Nuclear Information System (INIS)

    Ross, W.A.; Schneider, K.J.; Swanson, J.L.; Yasutake, K.M.; Allen, R.P.

    1985-07-01

    This document provides a comparison of six treatment options for transuranic wastes (TRUW) resulting from the reprocessing of commercial spent fuel. Projected transuranic waste streams from the Barnwell Nuclear Fuel Plant (BNFP), the reference fuel reprocessing plant in this report, were grouped into the five categories of hulls and hardware, failed equipment, filters, fluorinator solids, and general process trash (GPT) and sample and analytical cell (SAC) wastes. Six potential treatment options were selected for the five categories of waste. These options represent six basic treatment objectives: (1) no treatment, (2) minimum treatment (compaction), (3) minimum number of processes and products (cementing or grouting), (4) maximum volume reduction without decontamination (melting, incinerating, hot pressing), (5) maximum volume reduction with decontamination (decontamination, treatment of residues), and (6) noncombustible waste forms (melting, incinerating, cementing). Schemes for treatment of each waste type were selected and developed for each treatment option and each type of waste. From these schemes, transuranic waste volumes were found to vary from 1 m 3 /MTU for no treatment to as low as 0.02 m 3 /MTU. Based on conceptual design requirements, life-cycle costs were estimated for treatment plus on-site storage, transportation, and disposal of both high-level and transuranic wastes (and incremental low-level wastes) from 70,000 MTU. The study concludes that extensive treatment is warranted from both cost and waste form characteristics considerations, and that the characteristics of most of the processing systems used are acceptable. The study recommends that additional combinations of treatment methods or strategies be evaluated and that in the interim, melting, incineration, and cementing be further developed for commercial TRUW. 45 refs., 9 figs., 32 tabs

  8. Preliminary analysis of treatment strategies for transuranic wastes from reprocessing plants

    Energy Technology Data Exchange (ETDEWEB)

    Ross, W.A.; Schneider, K.J.; Swanson, J.L.; Yasutake, K.M.; Allen, R.P.

    1985-07-01

    This document provides a comparison of six treatment options for transuranic wastes (TRUW) resulting from the reprocessing of commercial spent fuel. Projected transuranic waste streams from the Barnwell Nuclear Fuel Plant (BNFP), the reference fuel reprocessing plant in this report, were grouped into the five categories of hulls and hardware, failed equipment, filters, fluorinator solids, and general process trash (GPT) and sample and analytical cell (SAC) wastes. Six potential treatment options were selected for the five categories of waste. These options represent six basic treatment objectives: (1) no treatment, (2) minimum treatment (compaction), (3) minimum number of processes and products (cementing or grouting), (4) maximum volume reduction without decontamination (melting, incinerating, hot pressing), (5) maximum volume reduction with decontamination (decontamination, treatment of residues), and (6) noncombustible waste forms (melting, incinerating, cementing). Schemes for treatment of each waste type were selected and developed for each treatment option and each type of waste. From these schemes, transuranic waste volumes were found to vary from 1 m/sup 3//MTU for no treatment to as low as 0.02 m/sup 3//MTU. Based on conceptual design requirements, life-cycle costs were estimated for treatment plus on-site storage, transportation, and disposal of both high-level and transuranic wastes (and incremental low-level wastes) from 70,000 MTU. The study concludes that extensive treatment is warranted from both cost and waste form characteristics considerations, and that the characteristics of most of the processing systems used are acceptable. The study recommends that additional combinations of treatment methods or strategies be evaluated and that in the interim, melting, incineration, and cementing be further developed for commercial TRUW. 45 refs., 9 figs., 32 tabs.

  9. Incorporating regulatory considerations into waste treatment technology development

    International Nuclear Information System (INIS)

    Siegel, M.R.; Powell, J.A.; Williams, T.A.; Kuusinen, T.L.; Lesperance, A.M.

    1991-02-01

    It is generally recognized that the development of new and innovative waste treatment technologies can significantly benefit the US Department of Energy's (DOE) environmental restoration and waste management program. DOE has established a research, development, demonstration, testing, and evaluation (RDDT ampersand E) program, managed by its Office of Technology Development, to encourage and direct the development of new waste treatment and management technologies. The treatment, storage, and disposal of hazardous and radioactive waste is heavily regulated both at the federal and state levels. In order to achieve the goals of applying the best new technologies in the fastest and most cost-effective manner possible, it is essential that regulatory factors be considered early and often during the development process. This paper presents a number of regulatory issues that are relevant to any program intended to encourage the development of new waste treatment and management technologies. It will also address how the use of these basic regulatory considerations can help ensure that technologies that are developed are acceptable to regulators and can therefore be deployed in the field. 2 refs

  10. Conceptual project of waste treatment plant of CDTN

    International Nuclear Information System (INIS)

    Gabriel, J.L.; Astolfi, D.

    1983-01-01

    This paper presents the conceptual project of the waste treatment plant of CDTN. Several areas, such as: process area, material entrance and exit area are studied. The treatment processes are: evaporation, filtration, cementation, cutting and processing of solid wastes. (C.M.)

  11. Waste water treatment by flotation

    Directory of Open Access Journals (Sweden)

    Camelia Badulescu

    2005-11-01

    Full Text Available The flotation is succesfully applied as a cleaning method of waste water refineries, textile fabrics (tissues, food industry, paper plants, oils plants, etc. In the flotation process with the released air, first of all, the water is saturated with air compressed at pressures between 0,3 – 3 bar, followed by the relaxed phenomenon of the air-water solution in a flotation cell with slowly flowing. The supersaturation could be applied in the waste water treatment. In this case the waste water, which is in the atmospheric equilibrum, is introduced in a closed space where the depression is 0,3 – 0,5 bar. Our paper presents the hypobaric flotation cell and the technological flow of cleaning of domestic waste waters

  12. Pediatric mandibular fractures treated by rigid internal fixation.

    Science.gov (United States)

    Wong, G B

    1993-09-01

    Mandibular fractures in the pediatric patient population are relatively uncommon. These patients present with their own unique treatment requirements. Most fractures have been treated conservatively by dental splints. Closed reduction techniques with maxillomandibular fixation (MMF) in very young children can pose several concerns, including cooperation, compliance and adequate nutritional intake. Rigid internal fixation of unstable mandibular fractures using miniplates and screws circumvents the need for MMF and allows immediate jaw mobilization. At major pediatric trauma institutions, there has been an increasing trend toward the use of this treatment when open reduction is necessary. This article presents a report of a five-year-old child who presented with bilateral mandibular fractures and was treated by rigid internal fixation and immediate mandibular mobilization.

  13. Review of the treatment of actinides-bearing radioactive wastes

    International Nuclear Information System (INIS)

    Krause, H.

    1983-01-01

    Actinides bearing wastes are produced above all in the course of irradiated nuclear fuel reprocessing and during fabrication of mixed oxide fuel elements. Particular attention in research and development work must be paid to this type of waste, mainly on account of its longevity. In practical application, the specific character of the actinides bearing wastes has been largely recognized. Nevertheless, definitions and methods of treatment generally accepted worldwide are still missing today. This has no bearing as yet on present day treatment of radioactive wastes. But by the time of application of the breeder technology at the latest a special treatment concept should be available which complies with the high actinide contents and short precooling periods of the wastes

  14. US Department of Energy interim mixed waste inventory report: Waste streams, treatment capacities and technologies

    International Nuclear Information System (INIS)

    1993-04-01

    The United States Department of Energy (DOE) has prepared this report to provide an inventory of its mixed wastes and treatment capacities and technologies in response to section 3021(a) of the Resource Conservation and Recovery Act (RCRA), as amended by section 105(a) of the Federal Facility Compliance Act (FFCA) of 1992 (Pub. L. No. 102-386). DOE has prepared this report for submission to EPA and the States in which DOE stores, generates, or treats mixed wastes. As required by the FFCA, this report contains: a national inventory of all mixed wastes in the DOE system that are currently stored or will be generated over the next five years, including waste stream name, description, EPA waste codes, basis for characterization (i.e., sampling and analysis or process knowledge), effect of radionuclides on treatment, quantity stored that is subject to the Land Disposal Restrictions (LDRs) storage prohibition, quantity stored that is not subject to the LDRS, expected generation over the next five years, Best Demonstrated Available Technology (BDAT) used for developing the LDR requirements, and waste minimization activities; and a national inventory of mixed waste treatment capacities and technologies, including information such as the descriptions, capacities, and locations of all existing and proposed treatment facilities, explanations for not including certain existing facilities in capacity evaluations, information to support decisions on unavailability of treatment technologies for certain mixed wastes, and the planned technology development activities

  15. Hazardous waste treatment and environmental remediation research

    International Nuclear Information System (INIS)

    1989-01-01

    Los Alamos National Laboratory (LANL) is currently evaluating hazardous waste treatment and environmental remediation technologies in existence and under development to determine applicability to remediation needs of the DOE facilities under the Albuquerque Operations Office and to determine areas of research need. To assist LANL is this effort, Science Applications International Corporation (SAIC) conducted an assessment of technologies and monitoring methods that have been demonstrated or are under development. The focus of this assessment is to: (1) identify existing technologies for hazardous waste treatment and environmental remediation of old waste sites; (2) identify technologies under development and the status of the technology; (3) assess new technologies that need development to provide adequate hazardous waste treatment and remedial action technologies for DOD and DOE sites; and (4) identify hazardous waste and remediation problems for environmental research and development. There are currently numerous research and development activities underway nationwide relating to environmental contaminants and the remediation of waste sites. To perform this effort, SAIC evaluated current technologies and monitoring methods development programs in EPA, DOD, and DOE, as these are the primary agencies through which developmental methods are being demonstrated. This report presents this evaluation and provides recommendations as to pertinent research needs or activities to address waste site contamination problems. The review and assessment have been conducted at a programmatic level; site-specific and contaminant-specific evaluations are being performed by LANL staff as a separate, related activity

  16. Permanganate Fixation of Plant Cells

    Science.gov (United States)

    Mollenhauer, Hilton H.

    1959-01-01

    In an evaluation of procedures explored to circumvent some of the problems of osmium tetroxide-fixation and methacrylate embedding of plant materials, excised segments of root tips of Zea mays were fixed for electron microscopy in potassium permanganate in the following treatment variations: unbuffered and veronal-acetate buffered solutions of 0.6, 2.0, and 5.0 per cent KMnO4 at pH 5.0, 6.0, 6.7, and 7.5, and temperatures of 2–4°C. and 22°C. After fixation the segments were dehydrated, embedded in epoxy resin, sectioned, and observed or photographed. The cells of the central region of the rootcap are described. The fixation procedures employing unbuffered solutions containing 2.0 to 5.0 per cent KMnO4 at a temperature of 22°C. gave particularly good preservation of cell structure and all membrane systems. Similar results were obtained using a solution containing 2.0 per cent KMnO4, buffered with veronal-acetate to pH 6.0, and a fixation time of 2 hours at 22°C. The fixation procedure utilizing veronal-acetate buffered, 0.6 per cent KMnO4 at 2–4°C. and pH 6.7 also gave relatively good preservation of most cellular constituents. However, preservation of the plasma membrane was not so good, nor was the intensity of staining so great, as that with the group of fixatives containing greater concentrations of KMnO4. The other fixation procedures did not give satisfactory preservation of fine structure. A comparison is made of cell structures as fixed in KMnO4 or OsO4. PMID:14423414

  17. Waste Treatment Technology Process Development Plan For Hanford Waste Treatment Plant Low Activity Waste Recycle

    International Nuclear Information System (INIS)

    McCabe, Daniel J.; Wilmarth, William R.; Nash, Charles A.

    2013-01-01

    The purpose of this Process Development Plan is to summarize the objectives and plans for the technology development activities for an alternative path for disposition of the recycle stream that will be generated in the Hanford Waste Treatment Plant Low Activity Waste (LAW) vitrification facility (LAW Recycle). This plan covers the first phase of the development activities. The baseline plan for disposition of this stream is to recycle it to the WTP Pretreatment Facility, where it will be concentrated by evaporation and returned to the LAW vitrification facility. Because this stream contains components that are volatile at melter temperatures and are also problematic for the glass waste form, they accumulate in the Recycle stream, exacerbating their impact on the number of LAW glass containers. Approximately 32% of the sodium in Supplemental LAW comes from glass formers used to make the extra glass to dilute the halides to acceptable concentrations in the LAW glass, and reducing the halides in the Recycle is a key component of this work. Additionally, under possible scenarios where the LAW vitrification facility commences operation prior to the WTP Pretreatment facility, this stream does not have a proven disposition path, and resolving this gap becomes vitally important. This task seeks to examine the impact of potential future disposition of this stream in the Hanford tank farms, and to develop a process that will remove radionuclides from this stream and allow its diversion to another disposition path, greatly decreasing the LAW vitrification mission duration and quantity of glass waste. The origin of this LAW Recycle stream will be from the Submerged Bed Scrubber (SBS) and the Wet Electrostatic Precipitator (WESP) from the LAW melter off-gas system. The stream is expected to be a dilute salt solution with near neutral pH, and will likely contain some insoluble solids from melter carryover or precipitates of scrubbed components (e.g. carbonates). The soluble

  18. Waste Treatment Technology Process Development Plan For Hanford Waste Treatment Plant Low Activity Waste Recycle

    Energy Technology Data Exchange (ETDEWEB)

    McCabe, Daniel J.; Wilmarth, William R.; Nash, Charles A.

    2013-08-29

    The purpose of this Process Development Plan is to summarize the objectives and plans for the technology development activities for an alternative path for disposition of the recycle stream that will be generated in the Hanford Waste Treatment Plant Low Activity Waste (LAW) vitrification facility (LAW Recycle). This plan covers the first phase of the development activities. The baseline plan for disposition of this stream is to recycle it to the WTP Pretreatment Facility, where it will be concentrated by evaporation and returned to the LAW vitrification facility. Because this stream contains components that are volatile at melter temperatures and are also problematic for the glass waste form, they accumulate in the Recycle stream, exacerbating their impact on the number of LAW glass containers. Approximately 32% of the sodium in Supplemental LAW comes from glass formers used to make the extra glass to dilute the halides to acceptable concentrations in the LAW glass, and reducing the halides in the Recycle is a key component of this work. Additionally, under possible scenarios where the LAW vitrification facility commences operation prior to the WTP Pretreatment facility, this stream does not have a proven disposition path, and resolving this gap becomes vitally important. This task seeks to examine the impact of potential future disposition of this stream in the Hanford tank farms, and to develop a process that will remove radionuclides from this stream and allow its diversion to another disposition path, greatly decreasing the LAW vitrification mission duration and quantity of glass waste. The origin of this LAW Recycle stream will be from the Submerged Bed Scrubber (SBS) and the Wet Electrostatic Precipitator (WESP) from the LAW melter off-gas system. The stream is expected to be a dilute salt solution with near neutral pH, and will likely contain some insoluble solids from melter carryover or precipitates of scrubbed components (e.g. carbonates). The soluble

  19. MOCVD waste gas treatment

    International Nuclear Information System (INIS)

    Geelen, A. van; Bink, P.H.M.; Giling, L.J.

    1993-01-01

    A large scale production of GaAs based solar cells with MOCVD will give rise to a considerable use of arsine. Therefore a gas treatment system is needed to convert the waste gases into less toxic compounds. In this study seven different gas treatment systems for MOCVD are compared by quantifying the environmental aspects. The systems are divided in wet systems, adsorption systems and thermal systems. The smallest amount of waste is produced by adsorption and thermal systems. Adsorption systems use the smallest amount of energy. The amount of primary materials used for the equipment varies per system. All systems are safe, but adsorption systems are simplest. At the moment, adsorption systems are probably the best choice from an environmental point of view. Nevertheless thermal systems have some potential advantages which make them interesting for the future

  20. Grout treatment facility dangerous waste permit application

    International Nuclear Information System (INIS)

    1992-07-01

    The Grout Treatment Facility (GTF) will provide permanent disposal for approximately 43 Mgal of low-level radioactive liquid waste currently being stored in underground tanks on the Hanford Site. The first step in permanent disposal is accomplished by solidifying the liquid waste with cementitious dry materials. The resulting grout is cast within underground vaults. This report on the GTF contains information on the following: Geologic data, hydrologic data, groundwater monitoring program, information, detection monitoring program, groundwater characterization drawings, building emergency plan--grout treatment facility, response action plan for grout treatment facility, Hanford Facility contingency plan, training course descriptions, overview of the Hanford Facility Grout Performance, assessment, bland use and zoning map, waste minimization plan, cover design engineering report, and clay liners (ADMIXTURES) in semiarid environments

  1. Mixed and Low-Level Waste Treatment Facility project

    International Nuclear Information System (INIS)

    1992-04-01

    Mixed and low-level wastes generated at the Idaho National Engineering Laboratory (INEL) are required to be managed according to applicable State and Federal regulations, and Department of Energy Orders that provide for the protection of human health and the environment. The Mixed and Low-Level Waste Treatment Facility Project was chartered in 1991, by the Department of Energy to provide treatment capability for these mixed and low-level waste streams. The first project task consisted of conducting engineering studies to identify the waste streams, their potential treatment strategies, and the requirements that would be imposed on the waste streams and the facilities used to process them. This report, Appendix A, Environmental ampersand Regulatory Planning ampersand Documentation, identifies the regulatory requirements that would be imposed on the operation or construction of a facility designed to process the INEL's waste streams. These requirements are contained in five reports that discuss the following topics: (1) an environmental compliance plan and schedule, (2) National Environmental Policy Act requirements, (3) preliminary siting requirements, (4) regulatory justification for the project, and (5) health and safety criteria

  2. Waste treatment of ships. Change in understanding of wastes and trend of waste treatment systems; Senjo no haikibutsu shori. 1. Haikibutsu ni taisuru ninshiki no henka to shori hoshiki no doko

    Energy Technology Data Exchange (ETDEWEB)

    Inatomi, M. [Hitachi Zosen Corp., Osaka (Japan)

    1996-07-25

    This paper explains treatment of wastes produced in ships. Wastes produced in ships should be essentially treated on ships. Since storage and transport of difficult-to-treat wastes to harbor for land treatment is expensive, wastes produced in ships are treated on ships as much as possible. Combustibles such as waste oil, plastics, paper and wood fiber waste are treated by incinerator. Food waste is dumped into the sea after crushing by disposer. Excrement and urine are dumped into the sea through a waste water treatment plant. Oil content in oily bilge is burned after heating and vapor separation. Food waste is temporarily stored in ships because its dumping along the coast and into harbor is impossible. Kitchen refuse decomposer utilizing bacteria was proposed for ships. Press for used cans and crushing/thermal compaction/storage equipment for plastics were also put on the market. The primary regulation on diesel engine exhaust gas may be cleared by improvement of engine bodies. 1 ref., 1 fig., 1 tab.

  3. Seminar on waste treatment and disposal

    International Nuclear Information System (INIS)

    Sneve, Malgorzata Karpow; Snihs, Jan Olof

    1999-01-01

    Leading abstract. A seminar on radioactive waste treatment and disposal was held 9 - 14 November 1998 in Oskarshamn, Sweden. The objective of the seminar was to exchange information on national and international procedures, practices and requirements for waste management. This information exchange was intended to promote the development of a suitable strategy for management of radioactive waste in Northwest Russia to be used as background for future co-operation in the region. The seminar focused on (1) overviews of international co-operation in the waste management field and national systems for waste management, (2) experiences from treatment of low- and intermediate-level radioactive waste, (3) the process of determining the options for final disposal of radioactive waste, (4) experiences from performance assessments and safety analysis for repositories intended for low- and intermediate level radioactive waste, (5) safety of storage and disposal of high-level waste. The seminar was jointly organised and sponsored by the Swedish Radiation Protection Institute (SSI), the Norwegian Radiation Protection Authority (NRPA), the Nordic Nuclear Safety Research (NKS) and the European Commission. A Russian version of the report is available. In brief, the main conclusions are: (1) It is the prerogative of the Russian federal Government to devise and implement a waste management strategy without having to pay attention to the recommendations of the meeting, (2) Some participants consider that many points have already been covered in existing governmental documents, (3) Norway and Sweden would like to see a strategic plan in order to identify how and where to co-operate best, (4) There is a rigorous structure of laws in place, based on over-arching environmental laws, (5) Decommissioning of submarines is a long and complicated task, (6) There are funds and a desire for continued Norway/Sweden/Russia co-operation, (7) Good co-operation is already taking place

  4. Seminar on waste treatment and disposal

    Energy Technology Data Exchange (ETDEWEB)

    Sneve, Malgorzata Karpow; Snihs, Jan Olof

    1999-07-01

    Leading abstract. A seminar on radioactive waste treatment and disposal was held 9 - 14 November 1998 in Oskarshamn, Sweden. The objective of the seminar was to exchange information on national and international procedures, practices and requirements for waste management. This information exchange was intended to promote the development of a suitable strategy for management of radioactive waste in Northwest Russia to be used as background for future co-operation in the region. The seminar focused on (1) overviews of international co-operation in the waste management field and national systems for waste management, (2) experiences from treatment of low- and intermediate-level radioactive waste, (3) the process of determining the options for final disposal of radioactive waste, (4) experiences from performance assessments and safety analysis for repositories intended for low- and intermediate level radioactive waste, (5) safety of storage and disposal of high-level waste. The seminar was jointly organised and sponsored by the Swedish Radiation Protection Institute (SSI), the Norwegian Radiation Protection Authority (NRPA), the Nordic Nuclear Safety Research (NKS) and the European Commission. A Russian version of the report is available. In brief, the main conclusions are: (1) It is the prerogative of the Russian federal Government to devise and implement a waste management strategy without having to pay attention to the recommendations of the meeting, (2) Some participants consider that many points have already been covered in existing governmental documents, (3) Norway and Sweden would like to see a strategic plan in order to identify how and where to co-operate best, (4) There is a rigorous structure of laws in place, based on over-arching environmental laws, (5) Decommissioning of submarines is a long and complicated task, (6) There are funds and a desire for continued Norway/Sweden/Russia co-operation, (7) Good co-operation is already taking place.

  5. Destruction and waste treatment methods used in a chemical agent disposal project. Memorandum report

    Energy Technology Data Exchange (ETDEWEB)

    McAndless, J.; Fedor, V.; Kinderwater, T.

    1992-10-01

    This report describes the equipment and methods used to thermally decontaminate scrap metal and destroy stockpiles of nerve agents, mustard and lewisite chemical warfare agents. Mustard was destroyed by direct incineration whereas the nerve agents and lewisite were chemically neutralized. The arsenic waste from the lewisite neutralization process was chemically-fixated in concrete for final disposal by landfilling. The scrap metal was incinerated and rendered suitable for recycling into metal feedstock.

  6. Operative treatment of early infection after internal fixation of limb fractures (exclusive of severe open fractures).

    Science.gov (United States)

    Bonnevialle, P

    2017-02-01

    Early infection after open reduction and internal fixation (ORIF) of a limb bone is defined as bacteriologically documented, deep and/or superficial surgical-site infection (SSI) diagnosed within 6months after the surgical procedure. This interval is arbitrarily considered sufficient to obtain fracture healing. The treatment of early infection after ORIF should be decided by a multidisciplinary team. The principles are the same as for revision arthroplasty. Superficial SSIs should be differentiated from deep SSIs, based on the results of bacteriological specimens collected using flawless technique. A turning point in the local microbial ecology occurs around the third or fourth week, when a biofilm develops around metallic implants. This biofilm protects the bacteria. The treatment relies on both non-operative and operative measures, which are selected based on the time to occurrence of the infection, condition of the soft tissues, and stage of bone healing. Both the surgical strategy and the antibiotic regimen should be determined during a multidisciplinary discussion. When treating superficial SSIs after ORIF, soft-tissue management is the main challenge. The treatment differs according to whether the hardware is covered or exposed. Defects in the skin and/or fascia can be managed using reliable reconstructive surgery techniques, either immediately or after a brief period of vacuum-assisted closure. In deep SSIs, deciding whether to leave or to remove the hardware is difficult. If the hardware is removed, the fracture site can be stabilised provisionally using either external fixation or a cement rod. Once infection control is achieved, several measures can be taken to stimulate bone healing before the end of the classical 6-month interval. If the hardware was removed, then internal fixation must be performed once the infection is eradicated. Copyright © 2016. Published by Elsevier Masson SAS.

  7. Radiobiological waste treatment-ashing treatment and immobilization with cement

    Energy Technology Data Exchange (ETDEWEB)

    Shengtao, Feng; Li, Gong; Li, Cheng; Benli, Wang; Lihong, Wang [China Inst. for Radiation Protection, Taiyuan, Shanxi (China)

    1997-02-01

    This report describes the results of the study on the treatment of radioactive biological waste in the China Institute for Radiation Protection (CIRP). The possibility of radiobiological waste treatment was investigated by using a RAF-3 type rapid ashing apparatus together with the immobilization of the resulted ash. This rapid ashing apparatus, developed by CIRP, is usually used for pretreatment of samples prior to chemical analysis and physical measurements. The results show that it can ash 3 kg of animal carcasses a batch, the ashing time is 5-7 h and the ash content is less than 4 wt%. The ashing temperature not exceeding 450 deg. C was used without any risk of high losses of radionuclides. The ash from the rapid ashing apparatus was demonstrated to be immobilized with ordinary silicate cement. The optimum cement/ash/water formulation of the cemented waste form was 35 {+-} 5 wt% cement, 29 {+-} 2 wt% water, and 36 {+-} 6 wt% ash. The performance of the waste form was in compliance with the technical requirements except for impact resistance. Mixing additives in immobilization formulations can improve the performance of the cemented ash waste form. The additives chosen were DH{sub 4A} flow promoter as a cement additive and vermiculite or zeolite as a supplement. The recommended formulation, i.e. an improved formulation of the cemented ash waste form is that additives DH{sub 4A} flow promoter and vermiculite (or zeolite) are added on the ground of optimum cement/ash/water formulation of the cemented waste form, the dosage of water, DH{sub 4A} and vermiculite (or zeolite) is 70 wt%, 0.5 wt% and {<=} 5 wt% of the cement dosage, respectively. The cemented ash waste forms obtained meet all the requirements for disposal. (author). 12 refs, 7 figs, 13 tabs.

  8. Radiobiological waste treatment-ashing treatment and immobilization with cement

    International Nuclear Information System (INIS)

    Feng Shengtao; Gong Li; Cheng Li; Wang Benli; Wang Lihong

    1997-01-01

    This report describes the results of the study on the treatment of radioactive biological waste in the China Institute for Radiation Protection (CIRP). The possibility of radiobiological waste treatment was investigated by using a RAF-3 type rapid ashing apparatus together with the immobilization of the resulted ash. This rapid ashing apparatus, developed by CIRP, is usually used for pretreatment of samples prior to chemical analysis and physical measurements. The results show that it can ash 3 kg of animal carcasses a batch, the ashing time is 5-7 h and the ash content is less than 4 wt%. The ashing temperature not exceeding 450 deg. C was used without any risk of high losses of radionuclides. The ash from the rapid ashing apparatus was demonstrated to be immobilized with ordinary silicate cement. The optimum cement/ash/water formulation of the cemented waste form was 35 ± 5 wt% cement, 29 ± 2 wt% water, and 36 ± 6 wt% ash. The performance of the waste form was in compliance with the technical requirements except for impact resistance. Mixing additives in immobilization formulations can improve the performance of the cemented ash waste form. The additives chosen were DH 4A flow promoter as a cement additive and vermiculite or zeolite as a supplement. The recommended formulation, i.e. an improved formulation of the cemented ash waste form is that additives DH 4A flow promoter and vermiculite (or zeolite) are added on the ground of optimum cement/ash/water formulation of the cemented waste form, the dosage of water, DH 4A and vermiculite (or zeolite) is 70 wt%, 0.5 wt% and ≤ 5 wt% of the cement dosage, respectively. The cemented ash waste forms obtained meet all the requirements for disposal. (author). 12 refs, 7 figs, 13 tabs

  9. Waste Treatment & Immobilization Plant Project

    Data.gov (United States)

    Federal Laboratory Consortium — In southeastern Washington State, Bechtel National, Inc. is designing, constructing and commissioning the world's largest radioactive waste treatment plant for the...

  10. Effects of SO/sub 2/ on photosynthesis and nitrogen fixation

    Energy Technology Data Exchange (ETDEWEB)

    Haellgren, J E; Huss, K

    1975-06-15

    Responses of photosynthesis and nitrogen fixation to NaHSO/sub 3/ (10/sup -5/ to 5 x 10/sup -3/ M) were investigated in the lichen Stereocaulon paschale (L.) Fr. and the blue-green alga Anabaena cylindrica Lemmermann. The treatments were performed in buffered media with varying pH (5.8 to 8.1) and light conditions (0 to 32 W x m/sup -2/). The activities of the intact organisms were investigated, under the same environmental conditions, with /sup 14/C liquid scintillation and acetylene reduction techniques respectively. The nitrogen fixation proved to be more susceptible than photosynthesis, in both organisms, and in all cases treatments at pH 5.8 were more inhibitory than at higher pH-values. Treatment with 5 x 10/sup -4/ M NaHSO/sub 3/ at pH 5.8 caused no reduction of photosynthesis in S. paschale, while the inhibition of nitrogen fixation was 97%. For A. cylindrica the corresponding values were 40% and 75% respectively. Short-time treatments of A. cylindrica showed that the nitrogen fixation was more rapidly affected than photosynthesis. The inhibition of nitrogenase activity and CO/sub 2/-fixation was smaller in the dark and increased at higher light intensities. Both processes showed a good capacity for recovery after removal of the NaHSO/sub 3/ solution. Also the clumping ability of A. cylindrica was disturbed by NaHSO/sub 3/ treatments.

  11. Use of ionizing radiation in waste water treatment

    International Nuclear Information System (INIS)

    Cech, R.

    1976-01-01

    A survey is presented of methods and possibilities of applying ionizing radiation in industrial waste water treatment. The most frequently used radiation sources include the 60 Co and 137 Cs isotopes and the 90 Sr- 90 Y combined source. The results are reported and the methods used are described of waste water treatment by sedimenting impurities and decomposing organic and inorganic compounds by ionizing radiation. It was found that waste water irradiation accelerated sedimentation and decomposition processes. The doses used varied between 50 and 500 krads. Ionizing radiation may also be used in waste water disinfection in which the effects are used of radiation on microorganisms and of the synthesis of ozone which does not smell like normally used chlorine. The described methods are still controversial from the economic point of view but the cost of waste water treatment by irradiation will significantly be reduced by the use of spent fuel elements. (J.B.)

  12. Advanced mixed waste treatment project draft environmental impact statement

    International Nuclear Information System (INIS)

    1998-07-01

    The AMWTP DEIS assesses the potential environmental impacts associated with four alternatives related to the construction and operation of a proposed waste treatment facility at the INEEL. Four alternatives were analyzed: The No Action Alternative, the Proposed Action, the Non-Thermal Treatment Alternative, and the Treatment and Storage Alternative. The proposed AMWTP facility would treat low-level mixed waste, alpha-contaminated low-level mixed waste, and transuranic waste in preparation for disposal. Transuranic waste would be disposed of at the Waste isolation Pilot Plant in New Mexico. Low-level mixed waste would be disposed of at an approval disposal facility depending on decisions to be based on DOE's Final Waste Management Programmatic Environmental Impact Statement. Evaluation of impacts on land use, socio-economics, cultural resources, aesthetic and scenic resources, geology, air resources, water resources, ecological resources, noise, traffic and transportation, occupational and public health and safety, INEEL services, and environmental justice were included in the assessment. The AMWTP DEIS identifies as the Preferred Alternative the Proposed Action, which is the construction and operation of the AMWTP facility

  13. Experiences with treatment of mixed waste

    International Nuclear Information System (INIS)

    Dziewinski, J.; Marczak, S.; Smith, W.H.; Nuttall, E.

    1996-01-01

    During its many years of research activities involving toxic chemicals and radioactive materials, Los Alamos National Laboratory (Los Alamos) has generated considerable amounts of waste. Much of this waste includes chemically hazardous components and radioisotopes. Los Alamos chose to use an electrochemical process for the treatment of many mixed waste components. The electro-chemical process, which the authors are developing, can treat a great variety of waste using one type of equipment built at a moderate expense. Such a process can extract heavy metals, destroy cyanides, dissolve contamination from surfaces, oxidize toxic organic compounds, separate salts into acids and bases, and reduce the nitrates. All this can be accomplished using the equipment and one crew of trained operating personnel. Results of a treatability study of chosen mixed wastes from Los Alamos Mixed Waste Inventory are presented. Using electrochemical methods cyanide and heavy metals bearing wastes were treated to below disposal limits

  14. Experiences with treatment of mixed waste

    Energy Technology Data Exchange (ETDEWEB)

    Dziewinski, J.; Marczak, S.; Smith, W.H. [Los Alamos National Lab., NM (United States); Nuttall, E. [Univ. of New Mexico, Albuquerque, NM (United States). Chemical and Nuclear Engineering Dept.

    1996-04-10

    During its many years of research activities involving toxic chemicals and radioactive materials, Los Alamos National Laboratory (Los Alamos) has generated considerable amounts of waste. Much of this waste includes chemically hazardous components and radioisotopes. Los Alamos chose to use an electrochemical process for the treatment of many mixed waste components. The electro-chemical process, which the authors are developing, can treat a great variety of waste using one type of equipment built at a moderate expense. Such a process can extract heavy metals, destroy cyanides, dissolve contamination from surfaces, oxidize toxic organic compounds, separate salts into acids and bases, and reduce the nitrates. All this can be accomplished using the equipment and one crew of trained operating personnel. Results of a treatability study of chosen mixed wastes from Los Alamos Mixed Waste Inventory are presented. Using electrochemical methods cyanide and heavy metals bearing wastes were treated to below disposal limits.

  15. Treatment of NPP wastes using vitrification

    International Nuclear Information System (INIS)

    Sobolev, I.A.; Lifanov, F.A.; Stefanovsky, S.V.; Kobelev, A.P.; Savkin, A.E.; Kornev, V.I.

    1998-01-01

    Glass-based materials to immobilize various liquid and solid radioactive wastes generated at nuclear power plants (NPP) were designed. Glassy waste forms can be produced using electric melting including a cold crucible melting. Leach rate of cesium was found to be 10 -5 -10 -6 g/(cm 2 day) (IAEA technique). Volume reduction factor after vitrification reached 4-5. Various technologies for NPP waste vitrification were developed. Direct vitrification means feeding of source waste into the melter with formation of glassy waste form to be disposed. Joule heated ceramic melter, and cold crucible were tested. Process variables at treatment of Kursk, Chernobyl (RBMK), Kalinin, Novovoronezh (VVER) NPP wastes were determined. The most promising melter was found to be the cold crucible. Pilot plant based on the cold crucibles has been designed and constructed. Solid burnable NPP wastes are incinerated and slags are incorporated in glass. (author)

  16. Alternatives for managing wastes from reactors and post-fission operations in the LWR fuel cycle. Volume 2. Alternatives for waste treatment

    International Nuclear Information System (INIS)

    1976-05-01

    Volume II of the five-volume report is devoted to the description of alternatives for waste treatment. The discussion is presented under the following section titles: fuel reprocessing modifications; high-level liquid waste solidification; treatment and immobilization of chop-leach fuel bundle residues; treatment of noncombustible solid wastes; treatment of combustible wastes; treatment of non-high-level liquid wastes; recovery of transuranics from non-high-level wastes; immobilization of miscellaneous non-high-level wastes; volatile radioisotope recovery and off-gas treatment; immobilization of volatile radioisotopes; retired facilities (decontamination and decommissioning); and, modification and use of selected fuel reprocessing wastes

  17. Alternatives for managing wastes from reactors and post-fission operations in the LWR fuel cycle. Volume 2. Alternatives for waste treatment

    Energy Technology Data Exchange (ETDEWEB)

    1976-05-01

    Volume II of the five-volume report is devoted to the description of alternatives for waste treatment. The discussion is presented under the following section titles: fuel reprocessing modifications; high-level liquid waste solidification; treatment and immobilization of chop-leach fuel bundle residues; treatment of noncombustible solid wastes; treatment of combustible wastes; treatment of non-high-level liquid wastes; recovery of transuranics from non-high-level wastes; immobilization of miscellaneous non-high-level wastes; volatile radioisotope recovery and off-gas treatment; immobilization of volatile radioisotopes; retired facilities (decontamination and decommissioning); and, modification and use of selected fuel reprocessing wastes. (JGB)

  18. Treatment for hydrazine-containing waste water solution

    Science.gov (United States)

    Yade, N.

    1986-01-01

    The treatment for waste solutions containing hydrazine is presented. The invention attempts oxidation and decomposition of hydrazine in waste water in a simple and effective processing. The method adds activated charcoal to waste solutions containing hydrazine while maintaining a pH value higher than 8, and adding iron salts if necessary. Then, the solution is aerated.

  19. Clostridium perfringens infection complicating periprosthetic fracture fixation about the hip: successful treatment with early aggressive debridement.

    LENUS (Irish Health Repository)

    Baker, Joseph F

    2012-07-13

    Periprosthetic fracture and infection are both challenges following hip arthroplasty. We report the case of an 87 year old female who underwent open reduction and internal fixation of a periprosthetic femoral fracture. Her post-operative course was complicated by infection with Clostridium perfringens. Early aggressive antibiotic treatment and surgical debridement were successful, and allowed retention of the original components.

  20. National Institutes of Health: Mixed waste minimization and treatment

    International Nuclear Information System (INIS)

    1995-08-01

    The Appalachian States Low-Level Radioactive Waste Commission requested the US Department of Energy's National Low-Level Waste Management Program (NLLWMP) to assist the biomedical community in becoming more knowledgeable about its mixed waste streams, to help minimize the mixed waste stream generated by the biomedical community, and to identify applicable treatment technologies for these mixed waste streams. As the first step in the waste minimization process, liquid low-level radioactive mixed waste (LLMW) streams generated at the National Institutes of Health (NIH) were characterized and combined into similar process categories. This report identifies possible waste minimization and treatment approaches for the LLMW generated by the biomedical community identified in DOE/LLW-208. In development of the report, on site meetings were conducted with NIH personnel responsible for generating each category of waste identified as lacking disposal options. Based on the meetings and general waste minimization guidelines, potential waste minimization options were identified

  1. National Institutes of Health: Mixed waste minimization and treatment

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-08-01

    The Appalachian States Low-Level Radioactive Waste Commission requested the US Department of Energy`s National Low-Level Waste Management Program (NLLWMP) to assist the biomedical community in becoming more knowledgeable about its mixed waste streams, to help minimize the mixed waste stream generated by the biomedical community, and to identify applicable treatment technologies for these mixed waste streams. As the first step in the waste minimization process, liquid low-level radioactive mixed waste (LLMW) streams generated at the National Institutes of Health (NIH) were characterized and combined into similar process categories. This report identifies possible waste minimization and treatment approaches for the LLMW generated by the biomedical community identified in DOE/LLW-208. In development of the report, on site meetings were conducted with NIH personnel responsible for generating each category of waste identified as lacking disposal options. Based on the meetings and general waste minimization guidelines, potential waste minimization options were identified.

  2. Spinopelvic Dissociation: Comparison of Outcomes of Percutaneous versus Open Fixation Strategies

    Directory of Open Access Journals (Sweden)

    Jeffrey M. Pearson

    2018-01-01

    Full Text Available Introduction. Spinopelvic dissociation injuries are historically treated with open reduction with or without decompressive laminectomy. Recent technological advances have allowed for percutaneous fixation with indirect reduction. Herein, we evaluate outcomes and complications between patients treated with open reduction versus percutaneous spinopelvic fixation. Methods. Retrospective review of patients undergoing spinopelvic fixation from a single, level one trauma center from 2012 to 2017. Patient information regarding demographics, associated injuries, and treatment outcome measures was recorded and analyzed. All fractures were classified via the AO Spine classification system. Results. Thirty-one spinopelvic dissociations were identified: 15 treated with open and 16 with percutaneous techniques. The two treatment groups had similar preoperative characteristics including spinopelvic parameters (pelvic incidence and lumbar lordosis. Compared to open reduction internal fixation, percutaneous fixation of spinopelvic dissociation resulted in statistically significantly lower blood loss (171 cc versus 538 cc; p=0.0013. There were no significant differences in surgical site infections (p=0.48 or operating room time (p=0.66. Conclusion. Percutaneous fixation of spinopelvic dissociation is associated with significantly less blood loss. Treatment outcomes in terms of infection, length of stay, operative cost, and final alignment between the open and percutaneous group were similar.

  3. Technical solutions for waste treatment in the Belene project

    International Nuclear Information System (INIS)

    Büttner, K.; Eichhorn, H.

    2011-01-01

    Outline: In June 2010 NUKEM Technologies GmbH was awarded a contract from ATOMSTROYEXPORT JSC to perform the complete work package related to designing and completion of the equipment for treatment of radioactive waste on the turn-key basis for Belene NPP. Technical Solutions: Waste Streams and Technologies at UKC and UKS; Concentration Plant; Thermal Treatment of Resins Sorting Facility; Biological Waste Water Treatment; Conditioning – Cementation • Sorting of Radwaste; Plasma Facility; Grouting; Filter Press; Monitoring and Tracking

  4. [Case control study on therapeutic effects of dynamic external fixtor combined with limited internal fixation and cross K-wires fixation for the treatment of Pilon fractures of the proximal interphalangeal joint].

    Science.gov (United States)

    Miao, Dao-yi; Yang, Guo-jing; Zhang, Ling-zhou; Wu, Jian-wei

    2015-10-01

    To compare the clinical effects and safety of dynamic external fixtor combined with limited internal fixation and cross K-wires fixation for the treatment of close Pilon fractures of the proximal interphalangeal joint. From June 2012 to June 2014, totally 41 patients (45 fingers) with close interphalangeal joint Pilon fracture were treated by dynamic external fixtor combined with limited internal fixation or cross K-wires fixation, and all the patients were followed up. In the dynamic external fixtor combined with limited internal fixation group (group A), there were 21 patients with 22 fingers, including 12 males and 9 females, with an average of (30.6±5.6) years old. In the cross K-wires fixation group (group B), there were 20 patients with 23 fingers, including 11 males and 9 females, with an average of (30.1±5.3) years old. Regular re-examination of X-ray was performed to evaluate the active range of joint motion, fracture healing time, infection rate and postoperative joint motion pain. According to the evaluation criteria of upper extremity function issued by the Hand Surgery Society of Chinese Medical Association, the excellent and good cases of group A was up to 19 and 13 for group B. The evaluation results has significant differences (Z=2.558, P=0.011). The excellent and good rate of group A was obviously higher than that of group B. The average bone union time of group A was (7.9±2.1) weeks, and (8.1±2.3) weeks for group B. There was no significant difference on the mean healing time (t=-0.304, P=0.762). The infection fingers of group A was 5, and 1 for group B. The difference between the results was statistically significant (χ2=3.287, Pexternal fixtor combined with limited internal fixation is a reliable and effective method to treat Pilon fractures of the proximal interphalangeal joint. It allows early postoperative functional rehabilitation and restores the joint function.

  5. Challenges when performing economic optimization of waste treatment: A review

    International Nuclear Information System (INIS)

    Juul, N.; Münster, M.; Ravn, H.; Söderman, M. Ljunggren

    2013-01-01

    Highlights: • Review of main optimization tools in the field of waste management. • Different optimization methods are applied. • Different fractions are analyzed. • There is focus on different parameters in different geographical regions. • More research is needed which encompasses both recycling and energy solutions. - Abstract: Strategic and operational decisions in waste management, in particular with respect to investments in new treatment facilities, are needed due to a number of factors, including continuously increasing amounts of waste, political demands for efficient utilization of waste resources, and the decommissioning of existing waste treatment facilities. Optimization models can assist in ensuring that these investment strategies are economically feasible. Various economic optimization models for waste treatment have been developed which focus on different parameters. Models focusing on transport are one example, but models focusing on energy production have also been developed, as well as models which take into account a plant’s economies of scale, environmental impact, material recovery and social costs. Finally, models combining different criteria for the selection of waste treatment methods in multi-criteria analysis have been developed. A thorough updated review of the existing models is presented, and the main challenges and crucial parameters that need to be taken into account when assessing the economic performance of waste treatment alternatives are identified. The review article will assist both policy-makers and model-developers involved in assessing the economic performance of waste treatment alternatives

  6. Challenges when performing economic optimization of waste treatment: A review

    Energy Technology Data Exchange (ETDEWEB)

    Juul, N., E-mail: njua@dtu.dk [DTU Management, Risø Campus, Technical University of Denmark (Denmark); Münster, M., E-mail: maem@dtu.dk [DTU Management, Risø Campus, Technical University of Denmark (Denmark); Ravn, H., E-mail: hans.ravn@aeblevangen.dk [RAM-løse edb, Æblevangen 55, 2765 Smørum (Denmark); Söderman, M. Ljunggren, E-mail: maria.ljunggren@chalmers.se [Energy and Environment, Chalmers University of Technology, Gothenburg (Sweden); IVL Swedish Environmental Research Institute, Gothenburg (Sweden)

    2013-09-15

    Highlights: • Review of main optimization tools in the field of waste management. • Different optimization methods are applied. • Different fractions are analyzed. • There is focus on different parameters in different geographical regions. • More research is needed which encompasses both recycling and energy solutions. - Abstract: Strategic and operational decisions in waste management, in particular with respect to investments in new treatment facilities, are needed due to a number of factors, including continuously increasing amounts of waste, political demands for efficient utilization of waste resources, and the decommissioning of existing waste treatment facilities. Optimization models can assist in ensuring that these investment strategies are economically feasible. Various economic optimization models for waste treatment have been developed which focus on different parameters. Models focusing on transport are one example, but models focusing on energy production have also been developed, as well as models which take into account a plant’s economies of scale, environmental impact, material recovery and social costs. Finally, models combining different criteria for the selection of waste treatment methods in multi-criteria analysis have been developed. A thorough updated review of the existing models is presented, and the main challenges and crucial parameters that need to be taken into account when assessing the economic performance of waste treatment alternatives are identified. The review article will assist both policy-makers and model-developers involved in assessing the economic performance of waste treatment alternatives.

  7. Treatment of wastes from a central spent-fuel rod consolidation facility

    International Nuclear Information System (INIS)

    Ross, W.A.

    1986-01-01

    The consolidation of commercial spent-fuel rods at a central treatment facility (such as the proposed Monitored Retrievable Storage Facility) will generate several types of waste, which may require treatment and disposal. Eight alternatives for the treatment of the wastes have been evaluated as part of DOE's Nuclear Waste Treatment Program at the Pacific Northwest Laboratory. The evaluation considered the system costs, potential waste form requirements, and processing characteristics

  8. Hanford Site radioactive mixed waste thermal treatment initiative

    International Nuclear Information System (INIS)

    Place, B.G.; Riddelle, J.G.

    1993-03-01

    This paper is a progress report of current Westinghouse Hanford Company engineering activities related to the implementation of a program for the thermal treatment of the Hanford Site radioactive mixed waste. Topics discussed include a site-specific engineering study, the review of private sector capability in thermal treatment, and thermal treatment of some of the Hanford Site radioactive mixed waste at other US Department of Energy sites

  9. Plutonium Finishing Plant (PFP) Treatment and Storage Unit Waste Analysis Plan

    International Nuclear Information System (INIS)

    PRIGNANO, A.L.

    2000-01-01

    The purpose of this waste analysis plan (WAP) is to document waste analysis activities associated with the Plutonium Finishing Plant Treatment and Storage Unit (PFP Treatment and Storage Unit) to comply with Washington Administrative Code (WAC) 173-303-300(1), (2), (4)(a) and (5). The PFP Treatment and Storage Unit is an interim status container management unit for plutonium bearing mixed waste radiologically managed as transuranic (TRU) waste. TRU mixed (TRUM) waste managed at the PFP Treatment and Storage Unit is destined for the Waste Isolation Pilot Plant (WIPP) and therefore is not subject to land disposal restrictions [WAC 173-303-140 and 40 CFR 268]. The PFP Treatment and Storage Unit is located in the 200 West Area of the Hanford Facility, Richland Washington (Figure 1). Because dangerous waste does not include source, special nuclear, and by-product material components of mixed waste, radionuclides are not within the scope of this documentation. The information on radionuclides is provided only for general knowledge

  10. Process waste treatment system upgrades: Clarifier startup at the nonradiological wastewater treatment plant

    International Nuclear Information System (INIS)

    Lucero, A.J.; McTaggart, D.R.; Van Essen, D.C.; Kent, T.E.; West, G.D.; Taylor, P.A.

    1998-07-01

    The Waste Management Operations Division at Oak Ridge National Laboratory recently modified the design of a reactor/clarifier at the Nonradiological Wastewater Treatment Plant, which is now referred to as the Process Waste Treatment Complex--Building 3608, to replace the sludge-blanket softener/clarifier at the Process Waste Treatment Plant, now referred to as the Process Waste Treatment Complex-Building 3544 (PWTC-3544). This work was conducted because periodic hydraulic overloads caused poor water-softening performance in the PWTC-3544 softener, which was detrimental to the performance and operating costs of downstream ion-exchange operations. Over a 2-month time frame, the modified reactor/clarifier was tested with nonradiological wastewater and then with radioactive wastewater to optimize softening performance. Based on performance to date, the new system has operated more effectively than the former one, with reduced employee radiological exposure, less downtime, lower costs, and improved effluent quality

  11. Radioactive Bench-scale Steam Reformer Demonstration of a Monolithic Steam Reformed Mineralized Waste Form for Hanford Waste Treatment Plant Secondary Waste - 12306

    Energy Technology Data Exchange (ETDEWEB)

    Evans, Brent; Olson, Arlin; Mason, J. Bradley; Ryan, Kevin [THOR Treatment Technologies, LLC - 106 Newberry St. SW, Aiken, SC 29801 (United States); Jantzen, Carol; Crawford, Charles [Savannah River Nuclear Solutions (SRNL), LLC, Aiken, SC 29808 (United States)

    2012-07-01

    Hanford currently has 212,000 m{sup 3} (56 million gallons) of highly radioactive mixed waste stored in the Hanford tank farm. This waste will be processed to produce both high-level and low-level activity fractions, both of which are to be vitrified. Supplemental treatment options have been under evaluation for treating portions of the low-activity waste, as well as the liquid secondary waste from the low-activity waste vitrification process. One technology under consideration has been the THOR{sup R} fluidized bed steam reforming process offered by THOR Treatment Technologies, LLC (TTT). As a follow-on effort to TTT's 2008 pilot plant FBSR non-radioactive demonstration for treating low-activity waste and waste treatment plant secondary waste, TTT, in conjunction with Savannah River National Laboratory, has completed a bench scale evaluation of this same technology on a chemically adjusted radioactive surrogate of Hanford's waste treatment plant secondary waste stream. This test generated a granular product that was subsequently formed into monoliths, using a geo-polymer as the binding agent, that were subjected to compressibility testing, the Product Consistency Test and other leachability tests, and chemical composition analyses. This testing has demonstrated that the mineralized waste form, produced by co-processing waste with kaolin clay using the TTT process, is as durable as low-activity waste glass. Testing has shown the resulting monolith waste form is durable, leach resistant, and chemically stable, and has the added benefit of capturing and retaining the majority of Tc-99, I-129, and other target species at high levels. (authors)

  12. Innovative technologies for the treatment of hazardous and mixed wastes

    International Nuclear Information System (INIS)

    Eyman, L.D.; Anderson, T.D.

    1988-01-01

    The treatment, storage, and disposal of hazardous and mixed wastes incur significant costs for Department of Energy (DOE) installations. These wastes must be managed under strict environmental controls and regulations to prevent the possibility of migration of hazardous materials to the biosphere. Through the Hazardous Waste Remedial Actions Program, the DOE is seeking to develop innovative ways of improving current treatment technologies to eliminate the hazardous components of wastes, reduce waste management costs, and minimize the volume requiring disposal as hazardous or mixed waste. Sponsored projects progress from research and development to field demonstration. Among the innovative technologies under development are supercritical water oxidation of hazardous chemicals, microwave-assisted destruction of chlorinated hydrocarbons, paramagnetic separation of metals from waste, detoxification and reclamation of waste acid, nitrate destruction through calcination, treatment/disposal of reactive metals, and methodologies for encapsulation. Technologies at a demonstration phase include detoxification of mixed waste sludge, microbial degradation of polychlorinated biphenyls in soil, and the remediation process for a hydrocarbon spill. 14 refs

  13. Waste-to-energy, municipal solid waste treatment, and best available technology

    DEFF Research Database (Denmark)

    Wang, Zhenfeng; Ren, Jingzheng; Goodsite, Michael Evan

    2018-01-01

    The treatment of municipal solid waste (MSW) has become an urgently important task of many countries. This objective of this study is to present a novel group multi-attribute decision analysis method for prioritizing the MSW treatment alternatives based on the interval-valued fuzzy set theory...... (DEMATEL) method was developed to determine the weights of the evaluation criteria by considering the independent relationships among these criteria. The multi-actor interval-valued fuzzy grey relational analysis was developed to rank the waste-to-energy scenarios. Four alternative processes for MSW...

  14. Public health aspects of waste-water treatment

    International Nuclear Information System (INIS)

    Lund, E.

    1975-01-01

    Among the bacteria, viruses and parasites which may be found in waste-water and polluted waters, those that are pathogenic to man are briefly described. The efficiency of different conventional waste-water treatments in removing the pathogens is reviewed, as well as additional factors of importance for the presence of micro-organisms in recipient waters. It is concluded that at present for treated waters no conventional treatment results in an effluent free from pathogens if they are present in the original waste-water. This is also true for sludges apart from pasteurization. The importance to public health of the presence of pathogens in recipient waters is briefly discussed. (author)

  15. Short Segment Fixation Versus Short Segment Fixation With Pedicle Screws at the Fracture Level for Thoracolumbar Burst Fracture

    Directory of Open Access Journals (Sweden)

    Anghel S

    2014-04-01

    Full Text Available Objective: The most prevailing surgical procedure in the treatment of thoracolumbar burst fractures, Short Segment Fixation (SSF, is often followed by loss of correction or hardware failure which may be significant enough to require another surgical intervention. In order to take advantage of its benefits but to avoid or diminish the risk and impact of associated drawbacks, some other alternatives have been lately developed among which we refer to short segment fixation with intermediate screws (SSF+IS. This article provides a comparative picture over the effectiveness of the two above-mentioned surgical treatments, focusing on their potential to prevent the loss of correction.

  16. Mini-plate versus Kirschner wire internal fixation for treatment of metacarpal and phalangeal fractures in Chinese Han population: a meta-analysis.

    Science.gov (United States)

    Xu, Jiaming; Zhang, Changqing

    2014-04-11

    This meta-analysis aimed to compare the therapeutic effect of mini-plate versus Kirschner wire (K-wire) internal fixation on the treatment of metacarpal and phalangeal fractures among Chinese Han population. Databases of China National Knowledge Infrastructure (CNKI), Wanfang, Chinese VIP, PubMed, and Embase were retrieved for studies on mini-plate (case group) versus K-wire (control group) internal fixation for the treatment of metacarpal and phalangeal fractures among Chinese Han population. The odds ratio (OR) and standardized mean difference (SMD) at 95% confidence interval (CI) were used for estimating the effects of dichotomous data and continuous data, respectively. All statistical analyses were performed by Review Manager 5.2 software. A total of 18 studies involving 1,375 metacarpal or phalangeal fracture patients (709 cases and 666 controls) were included in the meta-analysis. There were significant differences in fracture healing time (SMD = -1.28; 95% CI: -1.81, -0.76), postoperative infection rate (OR = 0.25; 95% CI: 0.16, 0.39), complication incidence (OR = 0.24; 95% CI: 0.15, 0.38), and surgery time (SMD = 1.57; 95% CI: 0.76, 2.37) between the case and the control group, while no significant difference was found in hospital stays between these two groups (SMD = 0.43; 95% CI: -0.34, 1.20; P = 0.27). For the treatment of metacarpal or phalangeal fracture among Chinese Han population, mini-plate has advantages of shorter healing time and lower infection rate and complication incidence compared with K-wire internal fixation, while a longer surgery time than K-wire. In conclusion, mini-plate is prior than K-wire internal fixation for the treatment of metacarpal or phalangeal fracture among Chinese Han population.

  17. Hazardous Waste/Mixed Waste Treatment Building Safety Information Document (SID)

    International Nuclear Information System (INIS)

    Fatell, L.B.; Woolsey, G.B.

    1993-01-01

    This Safety Information Document (SID) provides a description and analysis of operations for the Hazardous Waste/Mixed Waste Disposal Facility Treatment Building (the Treatment Building). The Treatment Building has been classified as a moderate hazard facility, and the level of analysis performed and the methodology used are based on that classification. Preliminary design of the Treatment Building has identified the need for two separate buildings for waste treatment processes. The term Treatment Building applies to all these facilities. The evaluation of safety for the Treatment Building is accomplished in part by the identification of hazards associated with the facility and the analysis of the facility's response to postulated events involving those hazards. The events are analyzed in terms of the facility features that minimize the causes of such events, the quantitative determination of the consequences, and the ability of the facility to cope with each event should it occur. The SID presents the methodology, assumptions, and results of the systematic evaluation of hazards associated with operation of the Treatment Building. The SID also addresses the spectrum of postulated credible events, involving those hazards, that could occur. Facility features important to safety are identified and discussed in the SID. The SID identifies hazards and reports the analysis of the spectrum of credible postulated events that can result in the following consequences: Personnel exposure to radiation; Radioactive material release to the environment; Personnel exposure to hazardous chemicals; Hazardous chemical release to the environment; Events leading to an onsite/offsite fatality; and Significant damage to government property. The SID addresses the consequences to the onsite and offsite populations resulting from postulated credible events and the safety features in place to control and mitigate the consequences

  18. Hazardous Waste/Mixed Waste Treatment Building Safety Information Document (SID)

    Energy Technology Data Exchange (ETDEWEB)

    Fatell, L.B.; Woolsey, G.B.

    1993-04-15

    This Safety Information Document (SID) provides a description and analysis of operations for the Hazardous Waste/Mixed Waste Disposal Facility Treatment Building (the Treatment Building). The Treatment Building has been classified as a moderate hazard facility, and the level of analysis performed and the methodology used are based on that classification. Preliminary design of the Treatment Building has identified the need for two separate buildings for waste treatment processes. The term Treatment Building applies to all these facilities. The evaluation of safety for the Treatment Building is accomplished in part by the identification of hazards associated with the facility and the analysis of the facility`s response to postulated events involving those hazards. The events are analyzed in terms of the facility features that minimize the causes of such events, the quantitative determination of the consequences, and the ability of the facility to cope with each event should it occur. The SID presents the methodology, assumptions, and results of the systematic evaluation of hazards associated with operation of the Treatment Building. The SID also addresses the spectrum of postulated credible events, involving those hazards, that could occur. Facility features important to safety are identified and discussed in the SID. The SID identifies hazards and reports the analysis of the spectrum of credible postulated events that can result in the following consequences: Personnel exposure to radiation; Radioactive material release to the environment; Personnel exposure to hazardous chemicals; Hazardous chemical release to the environment; Events leading to an onsite/offsite fatality; and Significant damage to government property. The SID addresses the consequences to the onsite and offsite populations resulting from postulated credible events and the safety features in place to control and mitigate the consequences.

  19. Correlation between radwaste processing and hazardous waste treatment processes

    International Nuclear Information System (INIS)

    Block, O.U.J.; Tulipano, F.J.

    1988-01-01

    The basic framework under SARA has established that preferred remedies are those which permanently and significantly reduce toxicity, mobility or volume of wastes. In the 1970's radwaste process designs at power plants received pressure to satisfy essentially the same criteria when increased emphasis was placed on limited disposal sites which resulted in rapidly escalating disposal costs. This paper provides a historical perspective of radwaste experience and discusses valuable insight to hazardous waste treatment technologies. The radwaste system experience is discussed in terms of providing a source of proven and reliable technologies. Discussion is presented on specific radwaste processes which are applicable technologies for hazardous waste treatment. The technologies presented include (a) Solidification, (b) Evaporation, and (c) Incineration. Experience is presented which establishes assurance that the treatment technologies will provide a permanent remedy to hazardous waste treatment. This paper describes typical radwaste solidification, evaporation and incineration processes at power plants. The design requirements and implementation of radwaste equipment is correlated to design requirement of hazardous waste equipment. Specific discussion is provided on how the available process equipment can reduce toxicity, mobility, and volume of waste. Discussion is presented on how the standard off the shelf processing equipment needs to be modified for radwaste and hazardous waste applications

  20. Low level radioactive liquid waste treatment at ORNL

    International Nuclear Information System (INIS)

    Robinson, R.A.; Lasher, L.C.

    1977-01-01

    A new Process Waste Treatment Plant has been constructed at ORNL. The wastes are processed through a precipitation-clarification step and then through an ion exchange step to remove the low-level activity in the waste before discharge into White Oak Creek

  1. Safety Aspects of Nuclear Waste Treatment

    International Nuclear Information System (INIS)

    Glubrecht, H.

    1986-01-01

    In the nuclear fuel cycle - like in most other industrial processes - some waste is produced which can be harmful to the environment and has to be stored safely and isolated from the Biosphere. This radioactive waste can be compared with toxic chemical waste under many aspects, but it has some special features, some of which make its handling more difficult, others make it easier. The difficulties are that radioactive waste does not only affect living organisms after incorporation, but also from some distance through its radiation. Therefore this waste has not only to be encapsuled, but also shielded. At higher concentrations radioactive waste produces heat and this has to be continuously derived from the storage area. On the other hand the control of even extremely small amounts of radioactive waste is very much easier than that of toxic chemical waste due to the high sensitivity of radiation detection methods. Furthermore radioactive waste is not persistent like most of the chemical waste. Of course some components will decay only after millennia, but a high percentage of radioactive waste becomes inactive after days, weeks or years. An important feature of safety aspects related to nuclear waste is the fact that problems of its treatment and storage have been discussed from the very beginning of Nuclear Energy Technology - what has not been the case in relation to most other industrial wastes

  2. Economic and environmental optimization of waste treatment

    Energy Technology Data Exchange (ETDEWEB)

    Münster, M. [System Analysis Department, DTU Management Engineering, Technical University of Denmark, Frederiksborgvej 399, 4000 Roskilde (Denmark); Ravn, H. [RAM-løse edb, Æblevangen 55, 2765 Smørum (Denmark); Hedegaard, K.; Juul, N. [System Analysis Department, DTU Management Engineering, Technical University of Denmark, Frederiksborgvej 399, 4000 Roskilde (Denmark); Ljunggren Söderman, M. [IVL Swedish Environmental Research Institute, Box 53021, SE-40014 Gothenburg (Sweden); Chalmers University of Technology, SE-412 96 Gothenburg (Sweden)

    2015-04-15

    Highlights: • Optimizing waste treatment by incorporating LCA methodology. • Applying different objectives (minimizing costs or GHG emissions). • Prioritizing multiple objectives given different weights. • Optimum depends on objective and assumed displaced electricity production. - Abstract: This article presents the new systems engineering optimization model, OptiWaste, which incorporates a life cycle assessment (LCA) methodology and captures important characteristics of waste management systems. As part of the optimization, the model identifies the most attractive waste management options. The model renders it possible to apply different optimization objectives such as minimizing costs or greenhouse gas emissions or to prioritize several objectives given different weights. A simple illustrative case is analysed, covering alternative treatments of one tonne of residual household waste: incineration of the full amount or sorting out organic waste for biogas production for either combined heat and power generation or as fuel in vehicles. The case study illustrates that the optimal solution depends on the objective and assumptions regarding the background system – illustrated with different assumptions regarding displaced electricity production. The article shows that it is feasible to combine LCA methodology with optimization. Furthermore, it highlights the need for including the integrated waste and energy system into the model.

  3. Plant densities and modulation of symbiotic nitrogen fixation in soybean

    Directory of Open Access Journals (Sweden)

    Marcos Javier de Luca

    2014-06-01

    Full Text Available Soybean nitrogen (N demands can be supplied to a large extent via biological nitrogen fixation, but the mechanisms of source/sink regulating photosynthesis/nitrogen fixation in high yielding cultivars and current crop management arrangements need to be investigated. We investigated the modulation of symbiotic nitrogen fixation in soybean [Glycine max (L. Merrill] at different plant densities. A field trial was performed in southern Brazil with six treatments, including non-inoculated controls without and with N-fertilizer, both at a density of 320,000 plants ha−1, and plants inoculated with Bradyrhizobium elkanii at four densities, ranging from 40,000 to 320,000 plants ha−1. Differences in nodulation, biomass production, N accumulation and partition were observed at stage R5, but not at stage V4, indicating that quantitative and qualitative factors (such as sunlight infrared/red ratio assume increasing importance during the later stages of plant growth. Decreases in density in the inoculated treatments stimulated photosynthesis and nitrogen fixation per plant. Similar yields were obtained at the different plant densities, with decreases only at the very low density level of 40,000 plants ha−1, which was also the only treatment to show differences in seed protein and oil contents. Results confirm a fine tuning of the mechanisms of source/sink, photosynthesis/nitrogen fixation under lower plant densities. Higher photosynthesis and nitrogen fixation rates are capable of sustaining increased plant growth.

  4. Treatment of low- and intermediate-level liquid radioactive wastes

    International Nuclear Information System (INIS)

    1984-01-01

    This report aims at giving the reader details of the experience gained in the treatment of both low- and intermediate-level radioactive liquid wastes. The treatment comprises those operations to remove radioactivity from the wastes and those that change only its chemical composition, so as to permit its discharge. Considerable experience has been accumulated in the satisfactory treatment of such wastes. Although there are no universally accepted definitions for low- and intermediate-level liquid radioactive wastes, the IAEA classification (see section 3.2) is used in this report. The two categories differ from one another in the fact that for low-level liquids the actual radiation does not require shielding during normal handling of the wastes. Liquid wastes which are not considered in this report are those from mining and milling operations and the high-level liquid wastes resulting from fuel reprocessing. These are referred to in separate IAEA reports. Likewise, wastes from decommissioning operations are not within the scope of this report. Apart from the description of existing methods and facilities, this report is intended to provide advice to the reader for the selection of appropriate solutions to waste management problems. In addition, new and promising techniques which are either being investigated or being considered for the future are discussed

  5. Nonunion of the humerus following intramedullary nailing treated by Ilizarov hybrid fixation.

    Science.gov (United States)

    Raschke, M; Khodadadyan, C; Maitino, P D; Hoffmann, R; Südkamp, N P

    1998-02-01

    A case of a posttraumatic humeral shaft nonunion, after intramedullary stabilization with a Seidel nail, is presented. Severe osteoporosis, an oligotrophic nonunion, subclinical infection, and adhesive capsulitis of the glenohumeral joint were present. Due to the subclinical infection and severe osteoporosis, other major invasive therapeutic options such as intramedullary nailing or compression plating and bone grafting were not applicable. Nonoperative treatment was also not indicated secondary to the pain and disability present. External fixation with the Ilizarov hybrid fixator seemed to offer a minimally invasive treatment modality without the need of additional bone grafting. After fourteen weeks of "callus massage," consisting of closed alternating compression and distraction with an Ilizarov hybrid fixator, osseous consolidation was achieved. Eight months after Ilizarov treatment the patient had returned to work as a mechanic. At the one-year follow-up examination, the patient presented pain free and with near normal shoulder and elbow motion, with stable osseous consolidation of the humerus. In some cases of nonunion of the humerus shaft, when standard treatment options are not recommended, external fixation with an Ilizarov hybrid fixator may offer a salvage procedure with a successful clinical outcome.

  6. Nonunited humerus shaft fractures treated by external fixator augmented by intramedullary rod

    Directory of Open Access Journals (Sweden)

    Mahmoud A El-Rosasy

    2012-01-01

    Full Text Available Background: Nonunion of humeral shaft fractures after previously failed surgical treatment presents a challenging therapeutic problem especially in the presence of osteoporosis, bone defect, and joint stiffness. It would be beneficial to combine the use of external fixation technique and intramedullary rod in the treatment of such cases. The present study evaluates the results of using external fixator augmented by intramedullary rod and autogenous iliac crest bone grafting (ICBG for the treatment of humerus shaft nonunion following previously failed surgical treatment. Materials and Methods: Eighteen patients with atrophic nonunion of the humeral shaft following previous implant surgery with no active infection were included in the present study. The procedure included exploration of the nonunion, insertion of intramedullary rod (IM rod, autogenous ICBG and application of external fixator for compression. Ilizarov fixator was used in eight cases and monolateral fixator in ten cases. The monolateral fixator was preferred for females and obese patients to avoid abutment against the breast or chest wall following the use of Ilizarov fixator. The fixator was removed after clinical and radiological healing of the nonunion, but the IM rod was left indefinitely. The evaluation of results included both bone results (union rate, angular deformity and limb shortening and functional outcome using the University of California, Los Angeles (UCLA rating scale. Results: The mean follow-up was 35 months (range 24 to 52 months. Bone union was obtained in all cases. The functional outcome was satisfactory in 15 cases (83% and unsatisfactory in 3 cases (17% due to joint stiffness. The time to bone healing averaged 4.2 months (range 3 to 7 months. The external fixator time averaged 4.5 months (range 3.2 to 8 months. Superficial pin tract infection occurred in 39% (28/72 of the pins. No cases of nerve palsy, refracture, or deep infection were encountered

  7. Anaerobic digester for treatment of organic waste

    Energy Technology Data Exchange (ETDEWEB)

    Sharma, V. K. [Indian Insitute of Technology, Delhi (India)]|[ENEA, Centro Ricerche Trisaia, Matera (Italy); Fortuna, F.; Canditelli, M.; Cornacchia, G. [ENEA, Centro Ricerche Trisaia, Matera (Italy). Dipt. Ambiente; Farina, R. [ENEA, centro Ricerche ``Ezio Clementel``, Bologna (Italy). Dipt. Ambiente

    1997-09-01

    The essential features of both new and more efficient reactor systems and their appropriate applications for various organic waste management situations, description of several working plants are discussed in the present communication. It is hoped that significant development reported here would be useful in opening a new vista to the application of anaerobic biotechnology for the waste treatment of both low/high organic strength and specialized treatment for toxic substances, using appropriate anaerobic methods.

  8. Chemical precipitation processes for the treatment of aqueous radioactive waste

    International Nuclear Information System (INIS)

    1992-01-01

    Chemical precipitation by coagulation-flocculation and sedimentation has been commonly used for many years to treat liquid (aqueous) radioactive waste. This method allows the volume of waste to be substantially reduced for further treatment or conditioning and the bulk of the waste to de discharged. Chemical precipitation is usually applied in combination with other methods as part of a comprehensive waste management scheme. As with any other technology, chemical precipitation is constantly being improved to reduce cost to increase the effectiveness and safety on the entire waste management system. The purpose of this report is to review and update the information provided in Technical Reports Series No. 89, Chemical Treatment of Radioactive Wastes, published in 1968. In this report the chemical methods currently in use for the treatment of low and intermediate level aqueous radioactive wastes are described and illustrated. Comparisons are given of the advantages and limitations of the processes, and it is noted that good decontamination and volume reduction are not the only criteria according to which a particular process should be selected. Emphasis has been placed on the need to carefully characterize each waste stream, to examine fully the effect of segregation and the importance of looking at the entire operation and not just the treatment process when planning a liquid waste treatment facility. This general approach includes local requirements and possibilities, discharge authorization, management of the concentrates, ICRP recommendations and economics. It appears that chemical precipitation process and solid-liquid separation techniques will continue to be widely used in liquid radioactive waste treatment. Current research and development is showing that combining different processes in one treatment plant can provide higher decontamination factors and smaller secondary waste arisings. Some of these processes are already being incorporated into new and

  9. Treatment of DOE mixed wastes using commercial facilities

    International Nuclear Information System (INIS)

    Kramer, J.F.; Ross, M.A.; Dilday, D.R.

    1992-02-01

    In a demonstration program, Department of Energy (DOE) solid mixed wastes generated during uranium processing operations are characterized to define the unit operations required for treatment. The objectives included the implementation of these treatment operations utilizing a commercial Treatment, Storage and Disposal Facility (TSDF). In contracting for commercial hazardous and mixed waste treatment, it is important to characterize the waste beyond the identification of toxicity characteristic (TC) and radiological content. Performing treatability studies and verification of all the unit operations required for treatment is critical. The stream selected for this program was TC hazardous for barium (D005) and contaminated with both depleted and low enriched uranium. The program resulted in the generation of characterization data and treatment strategies. The characterization and treatability studies indicated that although a common unit operation was required to remove the toxic characteristic, multiple pretreatment operations were needed. Many of these operations do not exist at available TSDF's, rendering some portions of the stream untreatable using existing commercial TSDF's. For this project the need for pretreatment operations resulted in only a portion of the waste originally targeted for treatment being accepted for treatment at a commercial TSDF. The majority of the targeted stream could not be successfully treated due to lack of an off-site commercial treatment facility having the available equipment and capacity or with the correct combination of RCRA permits and radioactive material handling licenses. This paper presents a case study documenting the results of the project

  10. Using bentonite for NPP liquid waste treatment

    International Nuclear Information System (INIS)

    Bui Dang Hanh

    2015-01-01

    During operation, nuclear power plants (NPPs) release a large quantity of water waste containing radionuclides required treatment for protection of the radiation workers and the environment. This paper introduces processes used to treat water waste from Paks NPP in Hungary and it also presents the results of a study on the use of Vietnamese bentonite to remove radioactive Caesium from a simulated water waste containing Cs. (author)

  11. Waste water treatment in Bukkerup (VB)

    DEFF Research Database (Denmark)

    Thomsen, Rikke; Overgaard, Morten; Jørgensen, Michael Søgaard

    1999-01-01

    In connection to the new waste water plan of Tølløse municipal the technical and environmental board has suggested that Bukkerup get a sewer system which brings the waste water to the treatment plant for Tysinge. All though the residents would like to list alternative suggestions which improve...... the local water environment but is still competitive.In this report the alternatives are listed, e.i. root system plants, sand filters and mini treatment plants.The conclusion is that root system plants and a combination of root system plants and sand filters are better that the sewer system....

  12. Solid and liquid radioactive waste treatment

    International Nuclear Information System (INIS)

    Rzyski, B.M.

    1989-01-01

    The technology for the treatment of low - and intermediate-level radioactive solid and liquid wastes is somewhat extensive. Some main guidance on the treatment methods are shown, based on informations contained in technical reports and complementary documents. (author) [pt

  13. Radioactive Liquid Waste Treatment Facility: Environmental Information Document

    Energy Technology Data Exchange (ETDEWEB)

    Haagenstad, H.T.; Gonzales, G.; Suazo, I.L. [Los Alamos National Lab., NM (United States)

    1993-11-01

    At Los Alamos National Laboratory (LANL), the treatment of radioactive liquid waste is an integral function of the LANL mission: to assure U.S. military deterrence capability through nuclear weapons technology. As part of this mission, LANL conducts nuclear materials research and development (R&D) activities. These activities generate radioactive liquid waste that must be handled in a manner to ensure protection of workers, the public, and the environment. Radioactive liquid waste currently generated at LANL is treated at the Radioactive Liquid Waste Treatment Facility (RLWTF), located at Technical Area (TA)-50. The RLWTF is 30 years old and nearing the end of its useful design life. The facility was designed at a time when environmental requirements, as well as more effective treatment technologies, were not inherent in engineering design criteria. The evolution of engineering design criteria has resulted in the older technology becoming less effective in treating radioactive liquid wastestreams in accordance with current National Pollutant Discharge Elimination System (NPDES) and Department of Energy (DOE) regulatory requirements. Therefore, to support ongoing R&D programs pertinent to its mission, LANL is in need of capabilities to efficiently treat radioactive liquid waste onsite or to transport the waste off site for treatment and/or disposal. The purpose of the EID is to provide the technical baseline information for subsequent preparation of an Environmental Impact Statement (EIS) for the RLWTF. This EID addresses the proposed action and alternatives for meeting the purpose and need for agency action.

  14. Radioactive Liquid Waste Treatment Facility: Environmental Information Document

    International Nuclear Information System (INIS)

    Haagenstad, H.T.; Gonzales, G.; Suazo, I.L.

    1993-11-01

    At Los Alamos National Laboratory (LANL), the treatment of radioactive liquid waste is an integral function of the LANL mission: to assure U.S. military deterrence capability through nuclear weapons technology. As part of this mission, LANL conducts nuclear materials research and development (R ampersand D) activities. These activities generate radioactive liquid waste that must be handled in a manner to ensure protection of workers, the public, and the environment. Radioactive liquid waste currently generated at LANL is treated at the Radioactive Liquid Waste Treatment Facility (RLWTF), located at Technical Area (TA)-50. The RLWTF is 30 years old and nearing the end of its useful design life. The facility was designed at a time when environmental requirements, as well as more effective treatment technologies, were not inherent in engineering design criteria. The evolution of engineering design criteria has resulted in the older technology becoming less effective in treating radioactive liquid wastestreams in accordance with current National Pollutant Discharge Elimination System (NPDES) and Department of Energy (DOE) regulatory requirements. Therefore, to support ongoing R ampersand D programs pertinent to its mission, LANL is in need of capabilities to efficiently treat radioactive liquid waste onsite or to transport the waste off site for treatment and/or disposal. The purpose of the EID is to provide the technical baseline information for subsequent preparation of an Environmental Impact Statement (EIS) for the RLWTF. This EID addresses the proposed action and alternatives for meeting the purpose and need for agency action

  15. Minimally invasive surgical technique: Percutaneous external fixation combined with titanium elastic nails for selective treatment of tibial fractures.

    Science.gov (United States)

    Tu, Kai-Kai; Zhou, Xian-Ting; Tao, Zhou-Shan; Chen, Wei-Kai; Huang, Zheng-Liang; Sun, Tao; Zhou, Qiang; Yang, Lei

    2015-12-01

    Several techniques have been described to treat tibial fractures, which respectively remains defects. This article presents a novel intra- and extramedullary fixation technique: percutaneous external fixator combined with titanium elastic nails (EF-TENs system). The purpose of this study is to introduce this new minimally invasive surgical technique and selective treatment of tibial fractures, particularly in segmental fractures, diaphysis fractures accompanied with distal or proximal bone subfissure, or fractures with poor soft-tissue problems. Following ethical approval, thirty-two patients with tibial fractures were treated by the EF-TENs system between January 2010 and December 2012. The follow-up studies included clinical and radiographic examinations. All relevant outcomes were recorded during follow-up. All thirty-two patients were achieved follow-ups. According to the AO classification, 3 Type A, 9 Type B and 20 Type C fractures were included respectively. According to the Anderson-Gustilo classification, there were 5 Type Grade II, 3 Type Grade IIIA and 2 Type Grade IIIB. Among 32 patients, 8 of them were segmental fractures. 12 fractures accompanied with bone subfissure. Results showed no nonunion case, with an average time of 23.7 weeks (range, 14-32 weeks). Among them, there were 3/32 delayed union patients and 0/32 malunion case. 4/32 patients developed a pin track infection and no patient suffered deep infection. The external fixator was removed with a mean time of 16.7 weeks (range, 10-26 weeks). Moreover, only 1/32 patient suffered with the restricted ROM of ankle, none with the restricted ROM of knee. This preliminary study indicated that the EF-TENs system, as a novel intra- and extramedullary fixation technique, had substantial effects on selective treatment of tibial fractures. Copyright © 2015 Elsevier Ltd. All rights reserved.

  16. DOE evaluates nine alternative thermal technologies for treatment of mixed waste

    International Nuclear Information System (INIS)

    Anon.

    1995-01-01

    In June 1993, the U.S. Department of Energy's (DOE's) Office of Technology Development commissioned a study to evaluate 19 thermal technologies for treating DOE's mixed waste. The study was divided into two phases: Phase I evaluated ten conventional incineration techniques (primarily rotary kiln), and Phase II looked at nine innovative, alternative thermal treatment technologies. The treatment processes were evaluated as part of an integrated waste treatment system, which would include all of the facilities, equipment, and methods required to treat and dispose DOE mixed waste. The relative merits and life-cycle costs were then developed for each of the 19 waste treatment systems evaluated. The study also identified the additional research and development, demonstration, and testing/evaluation steps that would be necessary for the waste treatment systems to successfully treat DOE mixed waste. 3 tabs., 2 refs

  17. Mochovce waste treatment centre

    International Nuclear Information System (INIS)

    Sedliak, D.; Endrody, J.

    2000-01-01

    The first unit of the Mochovce NPP (WWER 440 MW) was put in a test operation in October 1998. The second unit with the same power output was put in the test operation in March 2000. The Nuclear Regulatory Authority of the Slovak Republic in its Decision No. 318/98 of 28 October 1998, by which an agreement with the operation of the Unit 1 of the Mochovce. Nuclear Power Plant was issued, requires to start the construction of the Liquid Radioactive Waste Treatment Centre until January 2004. The subject of this presentation is a system description of the Liquid Radioactive Waste (LRW) management in the Mochovce NPP. The initial part is dedicated to a short description of the radioactive waste management legislation requirements. Then the presentation continues with an information about the LRW production in the Mochovce NPP, LRW sources, chemical and radiochemical attributes, description of storage. The presentation also provides real values of its production in a comparison with the design data. The LRW production minimization principles are also mentioned there. Another part deals with the basic requirements for the technology proposal of the liquid RW treatment, especially concerning the acceptance criteria at the Republic RW Repository Mochovce. The final part is devoted to a short description of the investment procedure principles - design preparation levels and a proposed construction schedule of the centre. (authors)

  18. Characterization of the solid low level mixed waste inventory for the solid waste thermal treatment activity - III

    Energy Technology Data Exchange (ETDEWEB)

    Place, B.G., Westinghouse Hanford

    1996-09-24

    The existing thermally treatable, radioactive mixed waste inventory is characterized to support implementation of the commercial, 1214 thermal treatment contract. The existing thermally treatable waste inventory has been identified using a decision matrix developed by Josephson et al. (1996). Similar to earlier waste characterization reports (Place 1993 and 1994), hazardous materials, radionuclides, physical properties, and waste container data are statistically analyzed. In addition, the waste inventory data is analyzed to correlate waste constituent data that are important to the implementation of the commercial thermal treatment contract for obtaining permits and for process design. The specific waste parameters, which were analyzed, include the following: ``dose equivalent`` curie content, polychlorinated biphenyl (PCB) content, identification of containers with PA-related mobile radionuclides (14C, 12 79Se, 99Tc, and U isotopes), tritium content, debris and non-debris content, container free liquid content, fissile isotope content, identification of dangerous waste codes, asbestos containers, high mercury containers, beryllium dust containers, lead containers, overall waste quantities, analysis of container types, and an estimate of the waste compositional split based on the thermal treatment contractor`s proposed process. A qualitative description of the thermally treatable mixed waste inventory is also provided.

  19. Offgas treatment for radioactive waste incinerators

    International Nuclear Information System (INIS)

    Stretz, L.A.; Koenig, R.A.

    1980-01-01

    Incineration of radioactive materials for resource recovery or waste volume reduction is recognized as an effective waste treatment method that will increase in usage and importance throughout the nuclear industry. The offgas cleanup subsystem of an incineration process is essential to ensure radionuclide containment and protection of the environment. Several incineration processes and associated offgas cleanup systems are discussed along with potential application of commercial pollution control components to radioactive service. Problems common to radioactive waste incinerator offgas service are identified and areas of needed research and development effort are noted

  20. Membrane Treatment of Liquid Salt Bearing Radioactive Wastes

    International Nuclear Information System (INIS)

    Dmitriev, S. A.; Adamovich, D. V.; Demkin, V. I.; Timofeev, E. M.

    2003-01-01

    The main fields of introduction and application of membrane methods for preliminary treatment and processing salt liquid radioactive waste (SLRW) can be nuclear power stations (NPP) and enterprises on atomic submarines (AS) utilization. Unlike the earlier developed technology for the liquid salt bearing radioactive waste decontamination and concentrating this report presents the new enhanced membrane technology for the liquid salt bearing radioactive waste processing based on the state-of-the-art membrane unit design, namely, the filtering units equipped with the metal-ceramic membranes of ''TruMem'' brand, as well as the electrodialysis and electroosmosis concentrators. Application of the above mentioned units in conjunction with the pulse pole changer will allow the marked increase of the radioactive waste concentrating factor and the significant reduction of the waste volume intended for conversion into monolith and disposal. Besides, the application of the electrodialysis units loaded with an ion exchange material at the end polishing stage of the radioactive waste decontamination process will allow the reagent-free radioactive waste treatment that meets the standards set for the release of the decontaminated liquid radioactive waste effluents into the natural reservoirs of fish-farming value

  1. Implementation of a management applied program for liquid radioactive waste treatment

    International Nuclear Information System (INIS)

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

    2003-01-01

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

  2. Gamma radiation treatment of waste waters from textile industries in ...

    African Journals Online (AJOL)

    Effects of gamma irradiation alone, and in combination with chemical treatment on color, odor, chemical oxyg-en demand (COD) and suspended solids in waste waters from textile industries in Ghana were studied to explore the potential of alternative and innovative processes for treatment of industrial waste waters. Waste ...

  3. Thermal treatment of municipal waste: An overview

    International Nuclear Information System (INIS)

    Sivaprasad, K.S.

    2010-01-01

    Waste generation, like a shadow accompanies all kinds of human activities. For a long time waste was ignored as of no consequence. Nevertheless in recent times the presence of Waste was felt by the adverse impact it began to have on human life. Attention was given to waste disposal. Various methods of disposal were developed. Actually a process of evolution was set in this area. Starting with Dumpsite it developed in to sanitary land fill. Adverse impact was beginning to be seen in leachate contaminating ground water, and long term emission of methane contributing to climate change. This set the thinking to seek other solutions. Waste was begun to be seen as a resource instead of a nuisance to be disposed off. Bio-methanation of waste for recovery of methane rich biogas was developed. The concept of thermal treatment of waste for disposal came in to being in order to reduce volume of disposal as only the ash will be disposed instead of the whole volume of waste when waste is subjected to thermal treatment. However, it was beset with certain pollution problems which needed to be addressed. Suitable pollution abatement systems were developed. In the meantime, with the increase in global population and lifestyle changes across the globe, demand for natural resources went up rapidly resulting in pressure on the finite resources of the earth. Emphasis shifted to recovery of value from waste while disposing. Recovery of Recyclables, and energy came in to focus. RDF technology was developed facilitating this making it possible to recover recyclables like plastics, metals etc besides generating the prepared fuel RDF for energy recovery. (Author)

  4. Lime treatment of liquid waste containing heavy metals, radionuclides and organics

    International Nuclear Information System (INIS)

    DuPont, A.

    1990-01-01

    This paper reports on lime treatment of liquid waste containing heavy metals, radio nuclides and organics. Lime is wellknown for its use in softening drinking water the treatment of municipal wastewaters. It is becoming important in the treatment of industrial wastewater and liquid inorganic hazardous waste; however, there are many questions regarding the use of lime for the treatment of liquid hazardous waste

  5. Handling and treatment of radioactive aqueous wastes

    International Nuclear Information System (INIS)

    1992-07-01

    This report aims to provide essential guidance to developing Member States without a nuclear power programme regarding selection, design and operation of cost effective treatment processes for radioactive aqueous liquids arising as effluents from small research institutions, hospitals and industries. The restricted quantities and low activity associated with the relevant wastes will generally permit contact-handling and avoid the need for shielding requirements. The selection of liquid waste treatment involves: Characterization of arising with the possibility of segregation; Discharge requirements for decontaminated liquors, both radioactive and non-radioactive; Available technologies and costs; Conditioning of the concentrates resulting from the treatment; Storage and disposal of the conditioned concentrates. The report will serve as a technical manual providing reference material and direct step-by-step know-how to staff in radioisotope user establishments and research centres in the developing Member States without nuclear power generation. Therefore, emphasis is limited to the simpler treatment facilities, which will be included with only the robust, well-established waste management processes carefully chosen as appropriate to developing countries. 20 refs, 12 figs, 7 tabs

  6. A prospective study of dynamic treatment of fracture phalanx and metacarpals of the hand with Kirschner-wire fixation/external fixator and finger splint: Daycare management (30 cases

    Directory of Open Access Journals (Sweden)

    Rahul Madhukar Salunkhe

    2016-01-01

    Full Text Available Introduction: Fractures of the phalanx and metacarpals are some of the most frequently encountered orthopedics injuries and constitute between 14-28% of all visits to emergency department which comprises 46% of the hand fracture and out of that mostly involved are the proximal phalanx and metacarpal neck fracture are most common and then the middle and distal phalanx and the base of metacarpal. The commonest complication with surgical treatment were stiff painful joints due to prolonged immobilization at fracture sites. This prospective study was undertaken to evaluate the functional outcome after surgical stabilization of metacarpal and phalanx fracture on day care basis. Materials And Methods: In our study we treated 30 patients who came to our hospital by fixation either with K wire or external fixation or hybrid fixation under local anaesthesia depending on the type of fracture between 2013 to 2014 with the average age 28 years with the youngest being 18 years and the oldest being 41 years with transverse, spiral, oblique closed fracture, grade 1 compound fracture, intraarticular, extraarticular, comminuted and non comminuted fracture of phalanx and metacarpals.These were day care treatment. Patient was allowed to begin his daily routine work from post operative day l. During this course the operated site was protected with splinting. Results: Clinical Outcomes were assessed as Excellent, Good, Satisfactory and Poor. Radiological assessment was done by taking x-ray to check radiological union.There were 24 cases had excellent outcome, 5 cases had good outcome and only 1 case had satisfactory outcome which occurred due to mal-union. There were 3 cases of pin-tract infection which subsided with oral antibiotics, and 3 cases of malunion. Conclusion: This was a day care procedure, patient were admitted, treated and discharged on the same day & encouraged to begin mobilization of the joints of hands from day 1.

  7. Evaluation of functional outcome of pilon fractures managed with limited internal fixation and external fixation: A prospective clinical study.

    Science.gov (United States)

    Meena, Umesh Kumar; Bansal, Mahesh Chand; Behera, Prateek; Upadhyay, Rahul; Gothwal, Gyan Chand

    2017-11-01

    The management of pilon fractures is controversial primarily due to the high rate of complications irrespective of the mode of treatment. Limited internal fixation with external fixation is associated with minimal soft tissue handling. This may reduce the chances of wound dehiscence and infection. This study was designed to evaluate the functional and clinical outcomes in patients treated with limited internal fixation combined with external fixation in pilon fractures. This study was conducted as a prospective clinical study on 56 skeletally mature patients with closed fractures with poor skin condition, and with open grade 1 and grade 2 distal tibial intra-articular fractures. All patients were treated with combined limited internal fixation and ankle spanning external fixation. All fractures in this series united with an average time period of union of 18.3weeks (ranging from 13 weeks to 30 weeks). There was no non-union in any case. There was malunion in 4 cases, varus malunion (>5 degree) in 2 cases and recurvatum in another 2 cases). Excellent to good functional results were observed in 88% cases based on the modified Ovadia and Beals score. The mean ankle dorsiflexion and planter flexion movements were 10.2±5.3 degrees and 27.4±7.2 degrees respectively. infections occurred in 6 patients which included 4 pin tract infections and 2 superficial wound infection, all 6 healed after removal of pin tract and with oral antibiotics. The technique of combined external fixation with internal fixation is safe and effective management option for intra-articular distal tibial fractures.

  8. [Treatment of thoracolumbar burst fracture with lateral anterior decompression, internal fixation with Ventrofix and bone graft with titanic mesh].

    Science.gov (United States)

    Zhang, Shi-min; Zhang, Zhao-jie; Liu, Yu-zhang; Zhang, Lu-tang; Li, Xing

    2011-11-01

    To discuss the efficacy of lateral anterior decompression, internal fixation with Ventrofix and bone graft with titanic mesh in the treatment of severe thoracolumbar burst fracture. From January 2008 to January 2010, 21 patients with severe thoracolumbar burst fracture were treated with lateral anterior decompression, internal fixation with Ventrofix, bone graft with titanic mesh. There were 15 males and 6 females, ranging in age from 21 to 46 years with an average of 32.2 years. Segment of fracture: 3 cases were in T11, 6 cases in T12, 7 cases in L1, 5 cases in L2. The mean kyphosis angle was 20.1 degrees and loading of fracture was 7.8 scores. Twenty-one cases accompany with incomplete paralysis. Nerves functions were observed according to Frankel grade; correction and maintain of kyphosis angle were observed by X-rays and CT. All the patients were followed up from 12 to 34 months with an average of 18.5 years. Postoperative complication including injury of pleura in 1 case, dynamic ileus in 2 cases, ilioinguinal nerve injury in 1 case, faulty union of wound in 1 case. All the above complications got recovery after symptomatic treatment. The mean kyphosis angle in fusional segment were 4.2 degrees and the rate of correction was 79%. Nerves functions of all patients got improvement and no internal fixation fail, kyphosis angle obviously lost, titanium mesh shifting, loosening and breakage of screw were found at final follow-up. Lateral anterior decompression, bone graft with titanic mesh, internal fixation with Ventrofix is an idea technique for severe thoracolumber burst fracture, but the method can not be used for patient with severity osteoporosis.

  9. Guide Of Treatment On Noxious Waste Of Experiment

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1987-05-15

    This book deals with environmental safe management and smooth driving of facilities, which indicates purpose of this guide, responsibility of environmental safe management, division of collect of starting point treatment, batch processing system, treatment of noxious waste of experiment, regulation of harmful waste such as medicine, corrosivity liquid, and treatment of cleaning solution of chrome-sulfuric acid, and regulation of Kyungpook National University Department Environmental Engineering Research Center, environmental protection law and the other related law.

  10. Guide Of Treatment On Noxious Waste Of Experiment

    International Nuclear Information System (INIS)

    1987-05-01

    This book deals with environmental safe management and smooth driving of facilities, which indicates purpose of this guide, responsibility of environmental safe management, division of collect of starting point treatment, batch processing system, treatment of noxious waste of experiment, regulation of harmful waste such as medicine, corrosivity liquid, and treatment of cleaning solution of chrome-sulfuric acid, and regulation of Kyungpook National University Department Environmental Engineering Research Center, environmental protection law and the other related law.

  11. Discharge and Treatment of Waste Water in Denmark

    DEFF Research Database (Denmark)

    Larsen, Torben

    1990-01-01

    This paper describes the waste water treatment situation in the area of Esbjerg. This example was chosen because the situation in Esbjerg is typical of that of most towns in Denmark, and because Esbjerg is closest to the British situation with respect to the receiving water. Esbjerg has...... a population of 70.000 inhabitans, and waste water treatment takes place in two treatment plants. These plants are now being extended to perform tertiary treatment, to fulfil the new Danish requirements. From 1992, the maximum average concentrations allowed for municipal waste water discharges to receiving...... waters will be; 15 mg/1 for BOD5, 8 mg/1 for total nitrogen, and 1.5 mg/1 for total phosphorus. These general requirements cover all types of receiving waters, but regional authorities have, in a number of cases, fixed lower values for sensitive areas....

  12. The Hanford Site solid waste treatment project; Waste Receiving and Processing (WRAP) Facility

    International Nuclear Information System (INIS)

    Roberts, R.J.

    1991-01-01

    The Waste Receiving and Processing (WRAP) Facility will provide treatment and temporary storage (consisting of in-process storage) for radioactive and radioactive/hazardous mixed waste. This facility must be constructed and operated in compliance with all appropriate US Department of Energy (DOE) orders and Resource Conservation and Recovery Act (RCRA) regulations. The WRAP Facility will examine and certify, segregate/sort, and treat for disposal suspect transuranic (TRU) wastes in drums and boxes placed in 20-yr retrievable storage since 1970; low-level radioactive mixed waste (RMW) generated and placed into storage at the Hanford Site since 1987; designated remote-handled wastes; and newly generated TRU and RMW wastes from high-level waste (HLW) recovery and processing operations. In order to accelerated the WRAP Project, a partitioning of the facility functions was done in two phases as a means to expedite those parts of the WRAP duties that were well understood and used established technology, while allowing more time to better define the processing functions needed for the remainder of WRAP. The WRAP Module 1 phase one, is to provide the necessary nondestructive examination and nondestructive assay services, as well as all transuranic package transporter (TRUPACT-2) shipping for both WRAP Project phases, with heating, ventilation, and air conditioning; change rooms; and administrative services. Phase two of the project, WRAP Module 2, will provide all necessary waste treatment facilities for disposal of solid wastes. 1 tab

  13. Radiation treatment of wastes: A review

    International Nuclear Information System (INIS)

    Feates, F.S.; George, D.

    1975-01-01

    Since 1945 over 70 papers have been published on various applications of radiation to waste treatment. Work carried out up to 1970 showed consistently that radiation is effective in degrading organic matter in wastes, destroying pathogenic organisms, and enhancing the sedimentation and filterability of sludges, but at a cost about ten times that of conventional treatment methods. Increased cost of energy, scarcity of potable water, environmental awareness and consequent legislation, and technical developments may be changing the picture. For example, ozone, already being widely used as an alternative to chlorine for sterilization, is claimed to be produced by gamma-irradiation of air or oxygen at half the cost of electrical methods. Radiation may solve specific problems associated with industrial wastes and evidence is reported of synergistic effects with oxygen and chlorine. In-situ reactivation of carbon used as an absorbent for textile dye wastes has been observed, and is being further studied. Prototype plant for complete sterilization of sewage sludge for use as fertilizer is in operation. Safety precautions necessary if large radiation sources are used by non-technical operatives will also be considered. (author)

  14. Effluent treatment and waste disposal

    International Nuclear Information System (INIS)

    1990-01-01

    In recent years there has been a great increase in the attention given to environmental matters by the public, media and Government. This has been reflected in the increased stature of environmental pressure groups and the introduction of new regulatory bodies and procedures. However, the satisfactory treatment and disposal of waste depends ultimately upon the development and employment of efficient low cost processes, and the enforcement of effective legislation. This Conference organised by the Yorkshire Branch of IChemE in association with the Institution's Environmental Protection Subject Group, will address the areas of waste monitoring, developments in pollution control processes and process economics and will look forward to future trends in waste disposal. It will also consider the impact of recent legislation upon the process industries. (author)

  15. Pyrolysis/Steam Reforming Technology for Treatment of TRU Orphan Wastes

    International Nuclear Information System (INIS)

    Mason, J. B.; McKibbin, J.; Schmoker, D.; Bacala, P.

    2003-01-01

    Certain transuranic (TRU) waste streams within the Department of Energy (DOE) complex cannot be disposed of at the Waste Isolation Pilot Plant (WIPP) because they do not meet the shipping requirements of the TRUPACT-II or the disposal requirements of the Waste Analysis Plan (WAP) in the WIPP RCRA Part B Permit. These waste streams, referred to as orphan wastes, cannot be shipped or disposed of because they contain one or more prohibited items, such as liquids, volatile organic compounds (VOCs), hydrogen gas, corrosive acids or bases, reactive metals, or high concentrations of polychlorinated biphenyl (PCB), etc. The patented, non-incineration, pyrolysis and steam reforming processes marketed by THOR Treatment Technologies LLC removes all of these prohibited items from drums of TRU waste and produces a dry, inert, inorganic waste material that meets the existing TRUPACT-II requirements for shipping, as well as the existing WAP requirements for disposal of TRU waste at WIPP. THOR Treatment Technologies is a joint venture formed in June 2002 by Studsvik, Inc. (Studsvik) and Westinghouse Government Environmental Services Company LLC (WGES) to further develop and deploy Studsvik's patented THORSM technology within the DOE and Department of Defense (DoD) markets. The THORSM treatment process is a commercially proven system that has treated over 100,000 cu. ft. of nuclear waste from commercial power plants since 1999. Some of this waste has had contact dose rates of up to 400 R/hr. A distinguishing characteristic of the THORSM process for TRU waste treatment is the ability to treat drums of waste without removing the waste contents from the drum. This feature greatly minimizes criticality and contamination issues for processing of plutonium-containing wastes. The novel features described herein are protected by issued and pending patents

  16. State-of-the-art report on low-level radioactive waste treatment

    International Nuclear Information System (INIS)

    Kibbey, A.H.; Godbee, H.W.

    1980-09-01

    An attempt is made to identify the main sources of low-level radioactive wastes that are generated in the United States. To place the waste problem in perspective, rough estimates are given of the annual amounts of each generic type of waste that is generated. Most of the wet solid wastes arise from the cleanup of gaseous and liquid radioactive streams prior to discharge or recycle. The treatment of the process streams and the secondary wet solid wastes thus generated is described for each type of government or fuel cycle installation. Similarly, the institutional wet wastes are also described. The dry wastes from all sources have smilar physical and chemical characteristics in that they can be classified as compactible, noncompactible, combustible, noncombustible, or combinations thereof. The various treatment options for concentrated or solid wet wastes and for dry wastes are discussed. Among the dry-waste treatment methods are compaction, baling, and incineration, as well as chopping, cutting, and shredding. Organic materials can usually be incinerated or, in some cases, biodegraded. The filter sludges, spent resins, incinerator ashes, and concentrated liquids are usually solidified in cement, urea-formaldehyde, or unsaturated polyester resins prior to burial. Asphalt has not yet been used as a solidificaton agent in the United States, but it probably will be used in the near future. The treatment of radioactive medical and bioresearch wastes is described, but the waste from radiochenmical, pharmaceutical, and other industries is not well defined at the present time. Recovery of waste metals and treatment of hazardous contaminated wastes are discussed briefly. Some areas appearing to need more research, development, and demonstration are specifically pointed out

  17. State-of-the-art report on low-level radioactive waste treatment

    Energy Technology Data Exchange (ETDEWEB)

    Kibbey, A.H.; Godbee, H.W.

    1980-09-01

    An attempt is made to identify the main sources of low-level radioactive wastes that are generated in the United States. To place the waste problem in perspective, rough estimates are given of the annual amounts of each generic type of waste that is generated. Most of the wet solid wastes arise from the cleanup of gaseous and liquid radioactive streams prior to discharge or recycle. The treatment of the process streams and the secondary wet solid wastes thus generated is described for each type of government or fuel cycle installation. Similarly, the institutional wet wastes are also described. The dry wastes from all sources have smilar physical and chemical characteristics in that they can be classified as compactible, noncompactible, combustible, noncombustible, or combinations thereof. The various treatment options for concentrated or solid wet wastes and for dry wastes are discussed. Among the dry-waste treatment methods are compaction, baling, and incineration, as well as chopping, cutting, and shredding. Organic materials can usually be incinerated or, in some cases, biodegraded. The filter sludges, spent resins, incinerator ashes, and concentrated liquids are usually solidified in cement, urea-formaldehyde, or unsaturated polyester resins prior to burial. Asphalt has not yet been used as a solidificaton agent in the United States, but it probably will be used in the near future. The treatment of radioactive medical and bioresearch wastes is described, but the waste from radiochenmical, pharmaceutical, and other industries is not well defined at the present time. Recovery of waste metals and treatment of hazardous contaminated wastes are discussed briefly. Some areas appearing to need more research, development, and demonstration are specifically pointed out.

  18. Low level radioactive waste disposal/treatment technology overview: Savannah River site

    International Nuclear Information System (INIS)

    Sturm, H.F. Jr.

    1987-01-01

    The Savannah River Site will begin operation of several low-level waste disposal/treatment facilities during the next five years, including a new low-level solid waste disposal facility, a low-level liquid effluent treatment facility, and a low-level liquid waste solidification process. Closure of a radioactive hazardous waste burial ground will also be completed. Technical efforts directed toward waste volume reduction include compaction, incineration, waste avoidance, and clean waste segregation. This paper summarizes new technology being developed and implemented. 11 refs., 1 fig

  19. Combustible radioactive waste treatment by incineration and chemical digestion

    International Nuclear Information System (INIS)

    Stretz, L.A.; Crippen, M.D.; Allen, C.R.

    1980-01-01

    A review is given of present and planned combustible radioactive waste treatment systems in the US. Advantages and disadvantages of various systems are considered. Design waste streams are discussed in relation to waste composition, radioactive contaminants by amount and type, and special operating problems caused by the waste

  20. Vitrification of TRU wastes at Rocky Flats Plant

    International Nuclear Information System (INIS)

    Williams, P.M.; Johnson, A.J.; Ledford, J.A.

    1979-01-01

    Immobilization of incinerator ash and various noncombustible TRU wastes was investigated. In three different research projects borosilicate glass proved to be the best candidate for TRU waste fixation. This glass has excellent chemical durability, long-term stability in the presence of radiation, and will withstand continuous temperatures up to 400 0 C without devitrification. In addition, wastes prepared in the form of glass will attain densities of approximately 2500 kg/m 3 (2.5 g/cc). The free forming method of producing glass buttons provides a very simple, consistent, low maintenance way of producing a final waste form for transporting and either retrievable or permanent storage for TRU waste. The vitrification process produces a durable glass from the low density ash generated by the fluidized bed incinerator process and provides volume and weight reductions that are superior to other fixation processes. This results in decreased transportation and storage costs

  1. Mixed and Low-Level Treatment Facility Project. Appendix B, Waste stream engineering files, Part 1, Mixed waste streams

    Energy Technology Data Exchange (ETDEWEB)

    1992-04-01

    This appendix contains the mixed and low-level waste engineering design files (EDFS) documenting each low-level and mixed waste stream investigated during preengineering studies for Mixed and Low-Level Waste Treatment Facility Project. The EDFs provide background information on mixed and low-level waste generated at the Idaho National Engineering Laboratory. They identify, characterize, and provide treatment strategies for the waste streams. Mixed waste is waste containing both radioactive and hazardous components as defined by the Atomic Energy Act and the Resource Conservation and Recovery Act, respectively. Low-level waste is waste that contains radioactivity and is not classified as high-level waste, transuranic waste, spent nuclear fuel, or 11e(2) byproduct material as defined by DOE 5820.2A. Test specimens of fissionable material irradiated for research and development only, and not for the production of power or plutonium, may be classified as low-level waste, provided the concentration of transuranic is less than 100 nCi/g. This appendix is a tool that clarifies presentation format for the EDFS. The EDFs contain waste stream characterization data and potential treatment strategies that will facilitate system tradeoff studies and conceptual design development. A total of 43 mixed waste and 55 low-level waste EDFs are provided.

  2. Mixed waste characterization, treatment, and disposal focus area. Technology summary

    International Nuclear Information System (INIS)

    1995-06-01

    This paper presents details about the technology development programs of the Department of Energy. In this document, waste characterization, thermal treatment processes, non-thermal treatment processes, effluent monitors and controls, development of on-site innovative technologies, and DOE business opportunities are applied to environmental restoration. The focus areas for research are: contaminant plume containment and remediation; mixed waste characterization, treatment, and disposal; high-level waste tank remediation; landfill stabilization; and decontamination and decommissioning

  3. Mixed waste characterization, treatment, and disposal focus area. Technology summary

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-06-01

    This paper presents details about the technology development programs of the Department of Energy. In this document, waste characterization, thermal treatment processes, non-thermal treatment processes, effluent monitors and controls, development of on-site innovative technologies, and DOE business opportunities are applied to environmental restoration. The focus areas for research are: contaminant plume containment and remediation; mixed waste characterization, treatment, and disposal; high-level waste tank remediation; landfill stabilization; and decontamination and decommissioning.

  4. Radioactive waste treatment technology at Czech nuclear power plants

    International Nuclear Information System (INIS)

    Kulovany, J.

    2001-01-01

    This presentation describes the main technologies for the treatment and conditioning of radioactive wastes at Czech nuclear power plants. The main technologies are bituminisation for liquid radioactive wastes and supercompaction for solid radioactive wastes. (author)

  5. Treatment of radioactive waste - Routine or challenge? Proceedings

    International Nuclear Information System (INIS)

    2003-01-01

    The seminar had the following topics: Proposal for new legislation covering radioactive waste management in the EU, new requirements preparations for the later repository, efficient and cost effective treatment of radioactive waste water, intermediate level waste cementation, incineration of spent ion exchange resins in a triphasic mixture, application of THOR-technology on resins, new development for transportation and storage of reactor vessel parts, and conditioning of nuclear fuel containing wastes. (uke)

  6. Nuclear waste management. Quarterly progress report, January-March 1980

    Energy Technology Data Exchange (ETDEWEB)

    Platt, A.M.; Powell, J.A. (comps.)

    1980-06-01

    Reported are: high-level waste immobilization, alternative waste forms, nuclear waste materials characterization, TRU waste immobilization, TRU waste decontamination, krypton solidification, thermal outgassing, iodine-129 fixation, unsaturated zone transport, well-logging instrumentation development, mobile organic complexes of fission products, waste management system and safety studies, assessment of effectiveness of geologic isolation systems, waste/rock interactions, engineered barriers, criteria for defining waste isolation, and spent fuel and pool component integrity. (DLC)

  7. ORNL process waste treatment plant modifications

    International Nuclear Information System (INIS)

    Bell, J.P.

    1982-01-01

    The ORNL Process Waste Treatment Plant removes low levels of radionuclides (primarily Cs-137 and Sr-90) from process waste water prior to discharge. The previous plant operation used a scavenging precipitaton - ion exchange process which produced a radioactive sludge. In order to eliminate the environmental problems associated with sludge disposal, the plant is being converted to a new ion exchange process without the precipitation process

  8. Mixed waste treatment capabilities at Envirocare

    International Nuclear Information System (INIS)

    Rafati, A.

    1994-01-01

    This presentation gives an overview of the business achievements and presents a corporate summary for the whole handling company Envirocare located in Clive, Utah. This company operates a permitted low-level radioactive and mixed waste facility which handles waste from the United States Department of Energy, Environmental Protection Agency, Department of Defense, and Fortune 500 companies. A description of business services and treatment capabilities is presented

  9. Treatment of tributyl phosphate wastes by extraction cum pyrolysis process

    International Nuclear Information System (INIS)

    Deshingkar, D.S.; Ramaswamy, M.; Kartha, P.K.S.; Kutty, P.V.E.; Ramanujam, A.

    1989-01-01

    For the treatment of spent tri n-butyl phospate (TBP) wastes from Purex process, a method involving extraction of TBP with phosphoric acid followed by pyrolysis of TBP - phosphoric acid phase was investigated. The process was examined with respect to simulated waste, process solvent wastes and aged organic waste samples. These studies seem to offer a simple treatment method for the separation of bulk of diluent from spent solvent wastes. The diluent phase needs further purification for reuse in reprocessing plant; otherwise it can be incinerated. (author). 18 refs., 3 tabs., 6 figs

  10. Advanced Off-Gas Control System Design For Radioactive And Mixed Waste Treatment

    International Nuclear Information System (INIS)

    Nick Soelberg

    2005-01-01

    Treatment of radioactive and mixed wastes is often required to destroy or immobilize hazardous constituents, reduce waste volume, and convert the waste to a form suitable for final disposal. These kinds of treatments usually evolve off-gas. Air emission regulations have become increasingly stringent in recent years. Mixed waste thermal treatment in the United States is now generally regulated under the Hazardous Waste Combustor (HWC) Maximum Achievable Control Technology (MACT) standards. These standards impose unprecedented requirements for operation, monitoring and control, and emissions control. Off-gas control technologies and system designs that were satisfactorily proven in mixed waste operation prior to the implementation of new regulatory standards are in some cases no longer suitable in new mixed waste treatment system designs. Some mixed waste treatment facilities have been shut down rather than have excessively restrictive feed rate limits or facility upgrades to comply with the new standards. New mixed waste treatment facilities in the U. S. are being designed to operate in compliance with the HWC MACT standards. Activities have been underway for the past 10 years at the INL and elsewhere to identify, develop, demonstrate, and design technologies for enabling HWC MACT compliance for mixed waste treatment facilities. Some specific off-gas control technologies and system designs have been identified and tested to show that even the stringent HWC MACT standards can be met, while minimizing treatment facility size and cost

  11. The status and developments of leather solid waste treatment: A mini-review.

    Science.gov (United States)

    Jiang, Huiyan; Liu, Junsheng; Han, Wei

    2016-05-01

    Leather making is one of the most widespread industries in the world. The production of leather goods generates different types of solid wastes and wastewater. These wastes will pollute the environment and threat the health of human beings if they are not well treated. Consequently, the treatment of pollution caused by the wastes from leather tanning is really important. In comparison with the disposal of leather wastewater, the treatment of leather solid wastes is more intractable. Hence, the treatment of leather solid wastes needs more innovations. To keep up with the rapid development of the modern leather industry, various innovative techniques have been newly developed. In this mini-review article, the major achievements in the treatment of leather solid wastes are highlighted. Emphasis will be placed on the treatment of chromium-tanned solid wastes; some new approaches are also discussed. We hope that this mini-review can provide some valuable information to promote the broad understanding and effective treatment of leather solid wastes in the leather industry. © The Author(s) 2016.

  12. Composite quarterly technical report: long-term high-level waste technology, October-December 1980

    International Nuclear Information System (INIS)

    Cornman, W.R.

    1981-04-01

    The technical information in this report summarizes work performed at participating sites to immobilize high-level radioactive wastes. The areas reported are in: program management and support; waste preparation; waste fixation; and final handling. Majority of the studies were in the area of waste fixation, some of which are: leaching tests of ceramic forms, high silica glass, graphite powder and other carbon preparations; viscosity measurements for a range of waste-glass compositions from references borosilicate glass to high-alumina glasses; neutron activation analysis for measuring leach rates; preparation of SYNROC D spheres; formulations for preparing ceramics from defense waste composition; development of a pilot-scale glass melter, and kinetic studies of slag formation in glass melters

  13. Radioactive waste treatment apparatus

    International Nuclear Information System (INIS)

    Abrams, R.F.; Chellis, J.G.

    1983-01-01

    Radioactive waste treatment apparatus is disclosed in which the waste is burned in a controlled combustion process, the ash residue from the combustion process is removed and buried, the gaseous effluent is treated in a scrubbing solution the pH of which is maintained constant by adding an alkaline compound to the solution while concurrently extracting a portion of the scrubbing solution, called the blowdown stream. The blowdown stream is fed to the incinerator where it is evaporated and the combustibles in the blowdown stream burned and the gaseous residue sent to the scrubbing solution. Gases left after the scrubbing process are treated to remove iodides and are filtered and passed into the atmosphere

  14. Treatment of organic radioactive waste in decommissioning project

    International Nuclear Information System (INIS)

    Dimovic, S.; Plecas, I.

    2003-01-01

    This paper describes methods of treatment of organic radioactive waste in the aspect of its integral part of radioactive waste which will arise during decommissioning process of nuclear power reactor RA (author)

  15. Treatment and conditioning of historical radioactive waste

    International Nuclear Information System (INIS)

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

    2009-01-01

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

  16. Process development for treatment of fluoride containing wastes

    Energy Technology Data Exchange (ETDEWEB)

    Singh, Mahesh; Kanvinde, V Y [Chemical Engineering Division, Bhabha Atomic Research Centre, Mumbai (India)

    1994-06-01

    Many chemical and metallurgical industries generate liquid wastes containing high values of fluorides in association of nitrates and other metals. Due to harmful effects of fluorides these type of wastes can not be disposed off in the environment without proper treatment. Bench-scale laboratory experiments were conducted to develop a process scheme to fix the fluorides as non-leachable solid waste and fluoride free treated liquid waste for their disposal. To optimize the important parameters, simulated synthetic and actual wastes were used. For this study, three waste streams were collected from Nuclear Fuel Complex, Hyderabad. (author). 6 tabs., 1 fig.

  17. Methodology development for radioactive waste treatment of CDTN/BR - liquid low-level radioactive wastes

    International Nuclear Information System (INIS)

    Morais, Carlos Antonio de

    1996-01-01

    The radioactive liquid wastes generated in Nuclear Technology Development Centre (CDTN) were initially treated by precipitation/filtration and then the resulting wet solid wastes were incorporated in cement. These wastes were composed of different chemicals and different radioactivities and were generated by different sectors. The objective of the waste treatment method was to obtain minimum wet solid waste volume and decontamination and minimum operational cost. The composition of the solid wastes were taken into consideration for compatible cementation process. Approximately 5,400 litres of liquid radioactive wastes were treated by this process during 1992-1995. The volume reduction was 1/24 th and contained 20% solids. (author)

  18. Conceptual design of the alcohol waste treatment equipment

    International Nuclear Information System (INIS)

    Fujisawa, Morio; Nitta, Kazuhiko; Morita, Yasuhiro; Nakada, Eiju

    2001-01-01

    This report describes the result of Conceptual Design of the Alcohol Waste Treatment Equipment. The experimental fast Reactor, JOYO, saves the radioactive alcohol waste at storage tank. As this alcohol waste is not able to treat with existing equipment, it is stored about 5 m 3 . And the amount of this is increasing every year. So it is necessary to treat the alcohol waste by chemical resolution for example. On account of this, the investigative test about filtration and dialyzer, and conceptual design about catalyst oxidation process, which is composed from head end process to resolution, are done. The results of investigation show as follows. 1. Investigative Test about filtration and dialyzer. (1) The electric conduction is suitable for the judgement of alkyl sodium hydrolysis Alkyl sodium hydrolysis is completed below 39% alcohol concentration. (2) The microfiltration is likely to separate the solid in alcohol waste. (3) From laboratory test, the electrodialyzer is effective for sodium separation in alcohol waste. And sodium remove rate, 96-99%, is confirmed. 2. Conceptual Design. The candidate process is as follows. (1) The head end process is electrodialyzer, and chemical resolution process is catalyst oxidation. (2) The head end process is not installed, and chemical resolution process is catalyst oxidation. (3) The head end process is electrodialyzer, and alcohol extracted by pervaporation. In this Conceptual Design, as far these process, the components, treatment ability, properties of waste, chemical mass balance, safety for fire and explosion, and the plot plan are investigated. As a result, remodeling the existing facility into catalyst oxidation process is effective to treat the alcohol waste, and treatment ability is about 1.25 l/h. (author)

  19. Risk assessment of CST-7 proposed waste treatment and storage facilities Volume I: Limited-scope probabilistic risk assessment (PRA) of proposed CST-7 waste treatment & storage facilities. Volume II: Preliminary hazards analysis of proposed CST-7 waste storage & treatment facilities

    Energy Technology Data Exchange (ETDEWEB)

    Sasser, K.

    1994-06-01

    In FY 1993, the Los Alamos National Laboratory Waste Management Group [CST-7 (formerly EM-7)] requested the Probabilistic Risk and Hazards Analysis Group [TSA-11 (formerly N-6)] to conduct a study of the hazards associated with several CST-7 facilities. Among these facilities are the Hazardous Waste Treatment Facility (HWTF), the HWTF Drum Storage Building (DSB), and the Mixed Waste Receiving and Storage Facility (MWRSF), which are proposed for construction beginning in 1996. These facilities are needed to upgrade the Laboratory`s storage capability for hazardous and mixed wastes and to provide treatment capabilities for wastes in cases where offsite treatment is not available or desirable. These facilities will assist Los Alamos in complying with federal and state requlations.

  20. China's Scientific Investigation for Liquid Waste Treatment Solutions

    International Nuclear Information System (INIS)

    Liangjin, B.; Meiqiong, L.; Kelley, D.

    2006-01-01

    Post World War II created the nuclear age with several countries developing nuclear technology for power, defense, space and medical applications. China began its nuclear research and development programs in 1950 with the establishment of the China Institute of Atomic Energy (CIAE) located near Beijing. CIAE has been China's leader in nuclear science and technical development with its efforts to create advanced reactor technology and upgrade reprocessing technology. In addition, with China's new emphasis on environmental safety, CIAE is focusing on waste treatment options and new technologies that may provide solutions to legacy waste and newly generated waste from the full nuclear cycle. Radioactive liquid waste can pose significant challenges for clean up with various treatment options including encapsulation (cement), vitrification, solidification and incineration. Most, if not all, nuclear nations have found the treatment of liquids to be difficult, due in large part to the high economic costs associated with treatment and disposal and the failure of some methods to safely contain or eliminate the liquid. With new environmental regulations in place, Chinese nuclear institutes and waste generators are beginning to seek new technologies that can be used to treat the more complex liquid waste streams in a form that is safe for transport and for long-term storage or final disposal. [1] In 2004, CIAE and Pacific Nuclear Solutions, a division of Pacific World Trade, USA, began discussions about absorbent technology and applications for its use. Preliminary tests were conducted at CIAE's Department of Radiochemistry using generic solutions, such as lubricating oil, with absorbent polymers for solidification. Based on further discussions between both parties, it was decided to proceed with a more formal test program in April, 2005, and additional tests in October, 2005. The overall objective of the test program was to apply absorbent polymers to various waste streams

  1. Environmental performance of an innovative waste refinery based on enzymatic treatment

    DEFF Research Database (Denmark)

    Tonini, Davide; Astrup, Thomas

    2011-01-01

    for virgin material and saving fossil resources. In this paper a life-cycle assessment of a pilot-scale waste refinery for the enzymatic treatment of municipal solid waste (MSW) is presented. The refinery produced a liquid (liquefied organic materials and paper) and a solid fraction (non-degradable materials......Decrease of fossil fuel dependence and global warming mitigation has become increasingly important issues during the last decades. With respect to waste management higher recycling rates for valuable materials as well as energy recovery from waste streams could play a significant role substituting......) from the waste. The waste refinery was compared to alternative treatments such as incineration, bioreactor landfill and mechanical-biological treatment followed by utilization of the RDF (refuse-derived fuel) for energy. The performance of the waste refinery turned out to be comparable...

  2. Safety Evaluation for Hull Waste Treatment Process in JNC

    International Nuclear Information System (INIS)

    Kojima, H.; Kurakata, K.

    2002-01-01

    Hull wastes and some scrapped equipment are typical radioactive wastes generated from reprocessing process in Tokai Reprocessing Plant (TRP). Because hulls are the wastes remained in the fuel shearing and dissolution, they contain high radioactivity. Japan Nuclear Cycle Development Institute (JNC) has started the project of Hull Waste Treatment Facility (HWTF) to treat these solid wastes using compaction and incineration methods since 1993. It is said that Zircaloy fines generated from compaction process might burn and explode intensely. Therefore explosive conditions of the fines generated in compaction process were measured. As these results, it was concluded that the fines generated from the compaction process were not hazardous material. This paper describes the outline of the treatment process of hulls and results of safety evaluation

  3. Grout Treatment Facility dangerous waste permit application

    International Nuclear Information System (INIS)

    1992-07-01

    The Grout Treatment Facility (GTF) is an existing treatment, storage, and/or disposal (TSD) unit located in the 200 East Area and the adjacent 600 Area of the Hanford Site. The GTF mixes dry cementitious solids with liquid mixed waste (containing both dangerous and radioactive constituents) produced by Hanford Site operations. The GTF consists of the following: The 241-AP-02D and 241-AP-04D waste pump pits and transfer piping; Dry Materials Facility (DMF); Grout Disposal Facility (GDF), consisting of the disposal vault and support and monitoring equipment; and Grout Processing Facility (GPF) and Westinghouse Hanford Company on the draft Hanford Facility Dangerous Waste Permit and may not be read to conflict with those comments. The Grout Treatment Facility Dangerous Waste Permit Application consists of both a Part A and a Part B permit application. An explanation of the Part A revisions associated with this TSD unit, including the current revision, is provided at the beginning of the Part A section. The Part B consists of 15 chapters addressing the organization and content of the Part B checklist prepared by the Washington State Department of Ecology (Ecology 1987). For ease of reference, the checklist section numbers, in brackets, follow chapter headings and subheadings

  4. [Surgical treatment for talar neck fracture of Hawkins III, IV type with compression hollow screws combined with external fixator].

    Science.gov (United States)

    Wang, Xian-Xun; Wan, Chang-Tao; Yu, Li

    2017-05-25

    To investigate the clinical effects of compression hollow screws combined with external fixator in treating talar neck fracture of Hawkins III, IV type. From March 2010 to August 2014, 15 patients with talar neck fractures of Hawkins III, IV type were treated by open reduction and compression hollow screws fixation complicated with external fixator fixation. Including 9 males and 6 females, aged from 17 to 65 years old with an average of 37.5 years old. There were 9 cases of Hawkins III and 6 cases of Hawkins IV type. Postoperative radiographs and CT of ankle were used to evaluate the fracture healing and talar necrosis. The function of ankle and foot were evaluated by American Society of Ankle and Foot Surgery(AOFAS). All the patients were followed up for 8 to 55 months with an average of 23.5 months and all fractures got bone healing from 13 to 38 weeks with an average of (17.99±6.81) weeks. Traumatic arthritis occurred in 7 cases and talar necrosis in 6 cases (2 cases of type III and 4 cases of type IV) after operation. The average AOFAS score was 61.80±18.75, including excellent in 4 cases, good in 2 cases, fair in 4 cases and poor in 5 cases. Talar neck fracture with Hawkins III, IV type has large possibility to develop avascular necrosis. Hollow compression screw combined with external fixation may late weight-bearing for ankle and can sufficiently guarantee bone healing time, and achieve good results for the treatment of talar neck fracture.

  5. Overview of non-thermal mixed waste treatment technologies: Treatment of mixed waste (ex situ); Technologies and short descriptions

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-07-01

    This compendium contains brief summaries of new and developing non- thermal treatment technologies that are candidates for treating hazardous or mixed (hazardous plus low-level radioactive) wastes. It is written to be all-encompassing, sometimes including concepts that presently constitute little more than informed ``ideas``. It bounds the universe of existing technologies being thought about or considered for application on the treatment of such wastes. This compendium is intended to be the very first step in a winnowing process to identify non-thermal treatment systems that can be fashioned into complete ``cradle-to-grave`` systems for study. The purpose of the subsequent systems paper studies is to investigate the cost and likely performance of such systems treating a representative sample of U.S. Department of Energy (DOE) mixed low level wastes (MLLW). The studies are called Integrated Non-thermal Treatment Systems (INTS) Studies and are being conducted by the Office of Science and Technology (OST) of the Environmental Management (EM) of the US Department of Energy. Similar studies on Integrated Thermal Treatment Systems have recently been published. These are not designed nor intended to be a ``downselection`` of such technologies; rather, they are simply a systems evaluation of the likely costs and performance of various non- thermal technologies that have been arranged into systems to treat sludges, organics, metals, soils, and debris prevalent in MLLW.

  6. Overview of non-thermal mixed waste treatment technologies: Treatment of mixed waste (ex situ); Technologies and short descriptions

    International Nuclear Information System (INIS)

    1995-07-01

    This compendium contains brief summaries of new and developing non- thermal treatment technologies that are candidates for treating hazardous or mixed (hazardous plus low-level radioactive) wastes. It is written to be all-encompassing, sometimes including concepts that presently constitute little more than informed ''ideas''. It bounds the universe of existing technologies being thought about or considered for application on the treatment of such wastes. This compendium is intended to be the very first step in a winnowing process to identify non-thermal treatment systems that can be fashioned into complete ''cradle-to-grave'' systems for study. The purpose of the subsequent systems paper studies is to investigate the cost and likely performance of such systems treating a representative sample of U.S. Department of Energy (DOE) mixed low level wastes (MLLW). The studies are called Integrated Non-thermal Treatment Systems (INTS) Studies and are being conducted by the Office of Science and Technology (OST) of the Environmental Management (EM) of the US Department of Energy. Similar studies on Integrated Thermal Treatment Systems have recently been published. These are not designed nor intended to be a ''downselection'' of such technologies; rather, they are simply a systems evaluation of the likely costs and performance of various non- thermal technologies that have been arranged into systems to treat sludges, organics, metals, soils, and debris prevalent in MLLW

  7. Intrascleral IOL Fixation.

    Science.gov (United States)

    Jacob, Soosan

    2017-01-01

    Intrascleral sutureless intraocular lens (IOL) fixation utilizes direct haptic fixation within the sclera in eyes with deficient capsular support. This has advantages of long-term stability, good control of tilt and decentration, and lesser pseudophakodonesis. This review summarizes various techniques for intrascleral haptic fixation, results, complications, adaptations in special situations, modifications of the technique, combination surgeries, and intrascleral capsular bag fixation techniques (glued capsular hook). Copyright 2017 Asia-Pacific Academy of Ophthalmology.

  8. Overview of DOE LLWMP waste treatment, packaging, and handling activities

    International Nuclear Information System (INIS)

    Pechin, W.H.

    1982-01-01

    The program objective is to develop the best available technology for waste treatment, packaging, and handling to meet the needs of shallow land burial disposal and for greater confinement than shallow land burial. The program has reviewed many of the hardware options for appropriate usage with low-level waste, but promising options remain to be evaluated. The testing of treatment technologies with actual radioactive process wastes has been initiated. The analysis of the interaction of treatment, solidification and disposal needs to be completed

  9. Treatment of unstable intraarticular fracture of distal radius: POP casting with external fixation.

    Science.gov (United States)

    ur Rahman, Obaid; Khan, Mohammad Qadeem; Rasheed, Haroon; Ahmad, Saleem

    2012-04-01

    To compare radiological and functional outcome of external fixation and distraction with conservative Plaster of Paris (POP) cast for unstable intra-articular fractures of the distal radius. The study was conducted on 60 patients with unstable intra-articular fracture of distal radius who reported to emergency or outpatient Orthopaedic Surgery department of Benazir Bhutto Hospital, Rawalpindi, between March and August 2007. They were divided into two equal groups: Group A and Group B, treated by Plaster of Paris cast, and external fixation with distraction respectively. The functional outcome in terms of freedom from pain, range of movement, grip power and deformity, and the radiological outcome of radial length, incongruity and radio-ulnar joint position were analysed at three months follow-up using a 3-point scoring scale. In Group A, 1 (3%) patient showed excellent result, 8 (27%) patients good results, 19 (63%) patients fair results and 2 (7%) patients poor result. In Group B, 14 (47%) patients showed excellent results, 11 (37%) patients good results, 4 (13%) patients fair results and 1 (3%) patient poor result. The outcome score of the Group B patients was significantly better compared to the Group A patients (p value advantages over conventional Plaster of Paris cast in the treatment of unstable intra-articular fractures of distal radius.

  10. Environmental and economic vision of plasma treatment of waste in Makkah

    Science.gov (United States)

    Galaly, Ahmed Rida; van Oost, Guido

    2017-10-01

    An environmental and economic assessment of the development of a plasma-chemical reactor equipped with plasma torches for the environmentally friendly treatment of waste streams by plasma is outlined with a view to the chemical and energetic valorization of the sustainability in the Kingdom of Saudi Arabia (KSA). This is especially applicable in the pilgrimage season in the city of Makkah, which is a major challenge since the amount of waste was estimated at about 750 thousand tons through Arabic Year 1435H (2015), and is growing at a rate of 3%-5% annually. According to statistics, the value of waste in Saudi Arabia ranges between 8 and 9 billion EUR. The Plasma-Treatment Project (PTP) encompasses the direct plasma treatment of all types of waste (from source and landfill), as well as an environmental vision and economic evaluation of the use of the gas produced for fuel and electricity production in KSA, especially in the pilgrimage season in the holy city Makkah. The electrical power required for the plasma-treatment process is estimated at 5000 kW (2000 kW used for the operation of the system and 3000 kW sold), taking into account the fact that: (1) the processing capacity of solid waste is 100 tons per day (2) and the sale of electricity amounts to 23.8 MW at 0.18 EUR per kWh. (3) The profit from the sale of electricity per year is estimated at 3.27 million EUR and the estimated profit of solid-waste treatment amounts to 6 million EUR per year and (4) the gross profit per ton of solid waste totals 8 million EUR per year. The present article introduces the first stage of the PTP, in Makkah in the pilgrimage season, which consists of five stages: (1) study and treatment of waste streams, (2) slaughterhouse waste treatment, (3) treatment of refuse-derived fuel, (4) treatment of car tires and (5) treatment of slag (the fifth stage associated with each stage from the four previous stages).

  11. Plasma technology for treatment of waste

    Energy Technology Data Exchange (ETDEWEB)

    Cohn, D [Massachusetts Inst. of Technology, Cambridge, MA (United States). Plasma Fusion Center

    1997-12-31

    Meeting goals for waste cleanup will require new technology with improved environmental attractiveness and reduced cost. Plasma technology appears promising because of the high degree of controllability; capability to process waste without the adverse effects of combustion; and a very wide temperature range of operation. At the Plasma Fusion Center at the Massachusetts Institute of Technology, a range of plasma technologies are being investigated. `Hot` thermal plasmas produced by DC arc technology are being examined for treatment of solid waste. In conjunction with this activity, new diagnostics are being developed for monitoring arc furnace operating parameters and gaseous emissions. Electron-beam generated plasma technology is being investigated as a means of producing non-thermal `cold` plasmas for selective processing of dilute concentrations of gaseous waste. (author). 4 figs., 5 refs.

  12. Evaluation of an external exposure of a worker during manipulation with waste packages stored in Bohunice radioactive waste treatment centre

    International Nuclear Information System (INIS)

    Slimak, A.; Hrncir, T.; Necas, V.

    2012-01-01

    The paper briefly describes current state of radioactive waste management as well as radioactive waste treatment and conditioning technologies used in Bohunice Radioactive Waste Treatment Centre. Radioactive Waste management includes pretreatment, treatment, conditioning, storage, transport and disposal of radioactive waste. Presented paper deals with the evaluation of an external exposure of a worker during manipulation with fibre-reinforced concrete container stored under shelter object. The external exposure of a worker was evaluated using VISIPLAN 3D ALARA code. (Authors)

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

    International Nuclear Information System (INIS)

    Trevorrow, L.

    1986-01-01

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

  14. Projected transuranic waste loads requiring treatment, storage, and disposal

    International Nuclear Information System (INIS)

    Hong, K.; Kotek, T.

    1996-01-01

    This paper provides information on the volume of TRU waste loads requiring treatment, storage, and disposal at DOE facilities for three siting configurations. Input consisted of updated inventory and generation data from. Waste Isolation Pilot plant Transuranic Waste Baseline Inventory report. Results indicate that WIPP's design capacity is sufficient for the CH TRU waste found throughout the DOE Complex

  15. Treatment of Atlantoaxial Rotatory Fixation With Botulinum Toxin Muscle Block and Manipulation

    Directory of Open Access Journals (Sweden)

    Chia-Hung Lin

    2010-04-01

    Full Text Available Slippage after reduction of atlantoaxial rotatory fixation (AARF is usually treated with repeated cervical traction and brace immobilization. To date, no data have been published on the management of muscle spasm during treatment. Here, we describe the case of a 7-year-old girl with AARF for 1 month who visited our hospital for treatment. During physical examination, spasm of the sternocleidomastoid muscle was noted. The patient was treated with manipulative reduction, and slippage after reduction was managed with botulinum spasticity block of the sternocleidomastoid and splenius capitis muscles, and repeated manipulation. Cervical orthosis immobilization with a rehabilitation program of isometric contract–relax exercise for the neck was conducted for 3 months. The subject had full recovery from AARF at 1-year follow-up. This report demonstrates that, in selected cases of slippage after reduction from AARF, conservative management with manipulation under anesthesia is a good method, and the muscle components may play a crucial role in AARF.

  16. Sodium-Bearing Waste Treatment, Applied Technology Plan

    International Nuclear Information System (INIS)

    Lance Lauerhass; Vince C. Maio; S. Kenneth Merrill; Arlin L. Olson; Keith J. Perry

    2003-01-01

    Settlement Agreement between the Department of Energy and the State of Idaho mandates treatment of sodium-bearing waste at the Idaho Nuclear Technology and Engineering Center within the Idaho National Engineering and Environmental Laboratory. One of the requirements of the Settlement Agreement is to complete treatment of sodium-bearing waste by December 31, 2012. Applied technology activities are required to provide the data necessary to complete conceptual design of four identified alternative processes and to select the preferred alternative. To provide a technically defensible path forward for the selection of a treatment process and for the collection of needed data, an applied technology plan is required. This document presents that plan, identifying key elements of the decision process and the steps necessary to obtain the required data in support of both the decision and the conceptual design. The Sodium-Bearing Waste Treatment Applied Technology Plan has been prepared to provide a description/roadmap of the treatment alternative selection process. The plan details the results of risk analyzes and the resulting prioritized uncertainties. It presents a high-level flow diagram governing the technology decision process, as well as detailed roadmaps for each technology. The roadmaps describe the technical steps necessary in obtaining data to quantify and reduce the technical uncertainties associated with each alternative treatment process. This plan also describes the final products that will be delivered to the Department of Energy Idaho Operations Office in support of the office's selection of the final treatment technology

  17. Sodium-Bearing Waste Treatment, Applied Technology Plan

    Energy Technology Data Exchange (ETDEWEB)

    Lance Lauerhass; Vince C. Maio; S. Kenneth Merrill; Arlin L. Olson; Keith J. Perry

    2003-06-01

    Settlement Agreement between the Department of Energy and the State of Idaho mandates treatment of sodium-bearing waste at the Idaho Nuclear Technology and Engineering Center within the Idaho National Engineering and Environmental Laboratory. One of the requirements of the Settlement Agreement is to complete treatment of sodium-bearing waste by December 31, 2012. Applied technology activities are required to provide the data necessary to complete conceptual design of four identified alternative processes and to select the preferred alternative. To provide a technically defensible path forward for the selection of a treatment process and for the collection of needed data, an applied technology plan is required. This document presents that plan, identifying key elements of the decision process and the steps necessary to obtain the required data in support of both the decision and the conceptual design. The Sodium-Bearing Waste Treatment Applied Technology Plan has been prepared to provide a description/roadmap of the treatment alternative selection process. The plan details the results of risk analyzes and the resulting prioritized uncertainties. It presents a high-level flow diagram governing the technology decision process, as well as detailed roadmaps for each technology. The roadmaps describe the technical steps necessary in obtaining data to quantify and reduce the technical uncertainties associated with each alternative treatment process. This plan also describes the final products that will be delivered to the Department of Energy Idaho Operations Office in support of the office's selection of the final treatment technology.

  18. Waste Treatment Plant - 12508

    Energy Technology Data Exchange (ETDEWEB)

    Harp, Benton; Olds, Erik [US DOE (United States)

    2012-07-01

    The Waste Treatment Plant (WTP) will immobilize millions of gallons of Hanford's tank waste into solid glass using a proven technology called vitrification. The vitrification process will turn the waste into a stable glass form that is safe for long-term storage. Our discussion of the WTP will include a description of the ongoing design and construction of this large, complex, first-of-a-kind project. The concept for the operation of the WTP is to separate high-level and low-activity waste fractions, and immobilize those fractions in glass using vitrification. The WTP includes four major nuclear facilities and various support facilities. Waste from the Tank Farms is first pumped to the Pretreatment Facility at the WTP through an underground pipe-in-pipe system. When construction is complete, the Pretreatment Facility will be 12 stories high, 540 feet long and 215 feet wide, making it the largest of the four major nuclear facilities that compose the WTP. The total size of this facility will be more than 490,000 square feet. More than 8.2 million craft hours are required to construct this facility. Currently, the Pretreatment Facility is 51 percent complete. At the Pretreatment Facility the waste is pumped to the interior waste feed receipt vessels. Each of these four vessels is 55-feet tall and has a 375,000 gallon capacity, which makes them the largest vessels inside the Pretreatment Facility. These vessels contain a series of internal pulse-jet mixers to keep incoming waste properly mixed. The vessels are inside the black-cell areas, completely enclosed behind thick steel-laced, high strength concrete walls. The black cells are designed to be maintenance free with no moving parts. Once hot operations commence the black-cell area will be inaccessible. Surrounded by black cells, is the 'hot cell canyon'. The hot cell contains all the moving and replaceable components to remove solids and extract liquids. In this area, there is ultrafiltration

  19. Performance estimates for waste treatment pyroprocesses in ATW

    International Nuclear Information System (INIS)

    Li, N.

    1997-01-01

    The author has identified several pyrometallurgical processes for the conceptual ATW waste treatment cycle. These processes include reductive extraction, electrowinning and electrorefining, which constitute some versatile treatment cycles for liquid-metal based and molten-salt based waste forms when they are properly integrated. This paper examines the implementation of these processes and the achievable separations for some typical species. The author also presents a simple analysis of the processing rates limited by mass diffusion through a thin hydrodynamic boundary layer. It is shown that these processes can be realized with compact and efficient devices to meet the ATW demand for the periodic feeding and cleaning of the waste

  20. Hanford Facility Dangerous Waste Permit Application, 200 Area Effluent Treatment Facility

    International Nuclear Information System (INIS)

    1993-08-01

    The 200 Area Effluent Treatment Facility Dangerous Waste Permit Application documentation consists of both Part A and a Part B permit application documentation. An explanation of the Part A revisions associated with this treatment and storage unit, including the current revision, is provided at the beginning of the Part A section. Once the initial Hanford Facility Dangerous Waste Permit is issued, the following process will be used. As final, certified treatment, storage, and/or disposal unit-specific documents are developed, and completeness notifications are made by the US Environmental Protection Agency and the Washington State Department of Ecology, additional unit-specific permit conditions will be incorporated into the Hanford Facility Dangerous Waste Permit through the permit modification process. All treatment, storage, and/or disposal units that are included in the Hanford Facility Dangerous Waste Permit Application will operate under interim status until final status conditions for these units are incorporated into the Hanford Facility Dangerous Waste Permit. The Hanford Facility Dangerous Waste Permit Application, 200 Area Effluent Treatment Facility contains information current as of May 1, 1993

  1. Hanford Facility Dangerous Waste Permit Application, 200 Area Effluent Treatment Facility

    Energy Technology Data Exchange (ETDEWEB)

    1993-08-01

    The 200 Area Effluent Treatment Facility Dangerous Waste Permit Application documentation consists of both Part A and a Part B permit application documentation. An explanation of the Part A revisions associated with this treatment and storage unit, including the current revision, is provided at the beginning of the Part A section. Once the initial Hanford Facility Dangerous Waste Permit is issued, the following process will be used. As final, certified treatment, storage, and/or disposal unit-specific documents are developed, and completeness notifications are made by the US Environmental Protection Agency and the Washington State Department of Ecology, additional unit-specific permit conditions will be incorporated into the Hanford Facility Dangerous Waste Permit through the permit modification process. All treatment, storage, and/or disposal units that are included in the Hanford Facility Dangerous Waste Permit Application will operate under interim status until final status conditions for these units are incorporated into the Hanford Facility Dangerous Waste Permit. The Hanford Facility Dangerous Waste Permit Application, 200 Area Effluent Treatment Facility contains information current as of May 1, 1993.

  2. Research and development of radioactive waste treatment methods

    International Nuclear Information System (INIS)

    Nguyen Thi Nang

    2000-01-01

    The Nuclear Research Institute (NRI) uses the reactor for research, training, isotope production and activation analyses. NRI generates about 150 m 3 of liquid and 5 m 3 of solid wastes every year. The researched methods applied to treatment of radwastes are coagulation-precipitation and two steps ion-exchange for liquid waste and compaction for solid waste are described. (author)

  3. Indications and outcome of Open Reduction and Internal Fixation of ...

    African Journals Online (AJOL)

    Background: Open reduction and internal fixation (ORIF) is a well-established surgical treatment of fractures worldwide. However, the indications and modes of stabilization of long bone fractures vary and are evolving .The general trend now is towards fixation with locked intramedullary nail (i.m nail) rather than plate and ...

  4. Strategies for the cost effective treatment of Oak Ridge legacy wastes

    International Nuclear Information System (INIS)

    Compere, A.L.; Griffith, W.L.; Huxtable, W.P.; Wilson, D.F.

    1998-03-01

    Research and development treatment strategies for treatment or elimination of several Oak Ridge plant liquid, solid, and legacy wastes are detailed in this report. Treatment strategies for volumetrically contaminated nickel; enriched uranium-contaminated alkali metal fluorides; uranium-contaminated aluminum compressor blades; large, mercury-contaminated lithium isotope separations equipment; lithium process chlorine gas streams; high-concentration aluminum nitrate wastes, and high-volume, low-level nitrate wastes are discussed. Research needed to support engineering development of treatment processes is detailed

  5. Treatment of stress fracture of the olecranon in throwing athletes with internal fixation through a small incision

    Directory of Open Access Journals (Sweden)

    Fujioka Hiroyuki

    2012-12-01

    Full Text Available Abstract The present study is a report of retrospective case series of stress fracture of the olecranon. Six patients presented posterior elbow pain in throwing in baseball and softball, but fracture was not diagnosed in radiographs. We detected stress fracture of the olecranon using computed tomographic (CT scan and treated the patient with internal fixation with a headless cannulated double threaded screw through a small skin incision. All patients returned to competitive level without elbow complaints after the operation. When throwing athletes present with unusual posterior elbow pain and no significant findings on radiographs, a CT scan examination should be performed. We recommend surgical treatment of internal fixation with a screw through a small skin incision, as a good option for stress fracture of the olecranon in order to allow early return to sports activity in competitive athletes.

  6. Treatment and disposal of low- and medium-level radioactive wastes in Hungary

    International Nuclear Information System (INIS)

    Berci, Karoly; Feher, Janos; Hemm, Bela; Setenyi, Marta

    1989-01-01

    Low- and medium-level radioactive wastes from the Paks Nuclear Power Plant, Hungary, are treated and disposed according to international and Hungarian regulations. Treatment of liquid wastes is accomplished by cementing, most of solid wastes are disposed after compaction. The forming of the final disposal site satisfies every radiation protection criteria. The recommendations of radioactive waste treatment are interpreted and analyzed in detail, for the implementation of advanced radioactive waste treatment techniques and facilities for treating and disposing of the liquid and solid wastes accumulated during operation of the PNPP. (R.P.) 8 figs.; 9 tabs

  7. Electrochemical treatment of mixed and hazardous waste

    International Nuclear Information System (INIS)

    Dziewinski, J.; Marczak, S.; Smith, W.; Nuttall, E.

    1995-01-01

    Los Alamos National Laboratory (LANL) and The University of New Mexico are jointly developing an electrochemical process for treating hazardous and radioactive wastes. The wastes treatable by the process include toxic metal solutions, cyanide solutions, and various organic wastes that may contain chlorinated organic compounds. The main component of the process is a stack of electrolytic cells with peripheral equipment such as a rectifier, feed system, tanks with feed and treated solutions, and a gas-venting system. During the treatment, toxic metals are deposited on the cathode, cyanides are oxidized on the anode, and organic compounds are anodically oxidized by direct or mediated electrooxidation, depending on their type. Bench scale experimental studies have confirmed the feasibility of applying electrochemical systems to processing of a great variety of hazardous and mixed wastes. The operating parameters have been defined for different waste compositions using surrogate wastes. Mixed wastes are currently treated at bench scale as part of the treatability study

  8. Innovative hazardous waste treatment technology

    International Nuclear Information System (INIS)

    Freeman, H.M.; Sferra, P.R.

    1990-01-01

    This book contains 21 various biodegradation techniques for hazardous waste treatment. Topics include: cyclic vertical water table movement for enhancement of in situ biodegradation of diesel fuel; enhanced biodegradation of petroleum hydrocarbons; and evaluation of aeration methods to bioremediate fuel-contaminated soils

  9. Waste water treatment plant city of Kraljevo

    Directory of Open Access Journals (Sweden)

    Marinović Dragan D.

    2016-01-01

    Full Text Available In all countries, in the fight for the preservation of environmental protection, water pollution, waste water is one of the very serious and complex environmental problems. Waste waters pollute rivers, lakes, sea and ground water and promote the development of micro-organisms that consume oxygen, which leads to the death of fish and the occurrence of pathogenic microbes. Water pollution and determination of its numerous microbiological contamination, physical agents and various chemical substances, is becoming an increasing health and general social problem. Purification of industrial and municipal waste water before discharge into waterways is of great importance for the contamination of the water ecosystems and the protection of human health. To present the results of purification of industrial and municipal wastewater in the city center Kraljevo system for wastewater treatment. The investigated physical and chemical parameters were performed before and after the city's system for wastewater treatment. The results indicate that the effect of purification present the physical and chemical parameters in waste water ranges from 0 - 19%.

  10. Treatment of Spinal Tuberculosis by Debridement, Interbody Fusion and Internal Fixation via Posterior Approach Only.

    Science.gov (United States)

    Tang, Ming-xing; Zhang, Hong-qi; Wang, Yu-xiang; Guo, Chao-feng; Liu, Jin-yang

    2016-02-01

    Surgical treatment for spinal tuberculosis includes focal tuberculosis debridement, segmental stability reconstruction, neural decompression and kyphotic deformity correction. For the lesions mainly involved anterior and middle column of the spine, anterior operation of debridement and fusion with internal fixation has been becoming the most frequently used surgical technique for the spinal tuberculosis. However, high risk of structural damage might relate with anterior surgery, such as damage in lungs, heart, kidney, ureter and bowel, and the deformity correction is also limited. Due to the organs are in the front of spine, there are less complications in posterior approach. Spinal pedicle screw passes through the spinal three-column structure, which provides more powerful orthopedic forces compared with the vertebral body screw, and the kyphotic deformity correction effect is better in posterior approach. In this paper, we report a 68-year-old male patient with thoracic tuberculosis who underwent surgical treatment by debridement, interbody fusion and internal fixation via posterior approach only. The patient was placed in prone position under general anesthesia. Posterior midline incision was performed, and the posterior spinal construction was exposed. Then place pedicle screw, and fix one side rod temporarily. Make the side of more bone destruction and larger abscess as lesion debridement side. Resect the unilateral facet joint, and retain contralateral structure integrity. Protect the spinal cord, nerve root. Clear sequestrum, necrotic tissue, abscess of paravertebral and intervertebral space. Specially designed titanium mesh cages or bone blocks were implanted into interbody. Fix both side rods and compress both sides to make the mesh cages and bone blocks tight. Reconstruct posterior column structure with allogeneic bone and autologous bone. Using this technique, the procedures of debridement, spinal cord decompression, deformity correction, bone grafting

  11. Shielding evaluation of the Thorium Lean Raffinate (TLR) waste treatment system at Waste Immobilisation Plant, Trombay

    International Nuclear Information System (INIS)

    Bhosale, Nitin A.; Deepa, A.K.; Jakhete, A.P.; Gopalakrishnan, R.K.; Prasad, S.K.; Gangadharan, Anand; Singh, Neelima

    2012-01-01

    Thoria rods irradiated in research reactors were reprocessed for 233 U recovery and resulted in 9 m 3 of acidic Th-bearing raffinate waste. A two step treatment system was planned to treat the raffinate waste. The first step was the generation of thorium lean raffinate waste (TLR) after separation of thorium and the second step was the separation of residual radioactivity and conditioning planned at WIP. The beta activity in the TLR waste is around 50 mCi/i having 137 Cs, 90 Sr and 125 Sb as its main constituents. Shielding calculations were carried out for the various stages of the treatment system at Area-61 of WIP, Trombay. Dose rate evaluations at each step of the treatment system were evaluated to keep the personnel exposure during campaign, ALARA. The work set the base for the shielding design of the treatment system and for the estimation of the man-rem budgeting during commissioning of the system

  12. Citrus processing waste water treatment

    Energy Technology Data Exchange (ETDEWEB)

    Hawash, S; Hafez, A J; El-Diwani, G

    1988-02-01

    The process utilizes biological treatment to decompose organic matter and decreases the COD to a value of 230 ppm, using 161 of air per 1 of treated waste water for a contact time of 2.5 h. Ozone is used subsequently for further purification of the waste water by destroying refractory organics. This reduces the COD to a value of 40 ppm, and consequently also lowers the BOD. Ozone also effectively removed the yellow-brown colour due to humic substances in dissolved or colloidal form; their oxidation leaves the water sparkling. Iron and manganese are also eliminated.

  13. Chemical treatment of radioactive wastes

    International Nuclear Information System (INIS)

    Pottier, P.E.

    1968-01-01

    This is the third manual of three commissioned by the IAEA on the three principal techniques used in concentrating radioactive liquid wastes, namely chemical precipitation, evaporation and ion exchange. The present manual deals with chemical precipitation by coagulation-flocculation and sedimentation, commonly called ''chemical treatment'' of low-activity wastes. Topics discussed in the manual are: (i) principles of coagulation on flocculation and sedimentation and associated processes; (ii) process and equipment; (iii) conditioning and disposal of flocculation sludge; (iv) sampling and the equipment required for experiments; and (v) factors governing the selection of processes. 99 refs, 17 figs, 4 tabs

  14. Mixed waste treatment options for wastes generated at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Garcia, E.C.

    1991-01-01

    The Idaho National Engineering Laboratory has generated mixed wastes (MWs) during its daily operations. MWs contain both radioactive and hazardous components, as defined by the Department of Energy and the Environmental Protection Agency. Treatment and disposal of stored MWs, as well as future generated MWs, are required to meet all regulations specified by the regulating agencies. This report reviews proven and emerging technologies that can treat MWs. It also provides a method for selection of the appropriate technology for treatment of a particular waste stream. The report selects for further consideration various treatments that can be used to treat MWs that fall under Land Disposal Restrictions. The selection methodology was used to arrive at these treatments. 63 refs., 7 figs., 23 tabs

  15. Development of treatment technologies for the processing of US Department of Energy mixed waste

    International Nuclear Information System (INIS)

    Backus, P.M.; Berry, J.B.; Coyle, G.J.; Lurk, P.W.; Wolf, S.M.

    1993-01-01

    Waste contaminated with chemically hazardous and radioactive species is defined as mixed waste. Significant technology development has been conducted for separate treatment of hazardous and radioactive waste, but technology development addressing mixed-waste treatment has been limited. Management of mixed waste requires treatment which must meet the standards established by the US Environmental Protection Agency for the specific hazardous constituents while also providing adequate control of the radionuclides. Technology has not been developed, demonstrated, or tested to produce a low-risk final waste form specifically for mixed waste. Throughout the US Department of Energy (DOE) complex, mixed waste is a problem because definitive treatment standards have not been established and few disposal facilities are available. Treatment capability and capacity are also limited. Site-specific solutions to the management of mixed waste have been initiated; however, site-specific programs result in duplication of technology development between various sites. Significant progress is being made in developing technology for mixed waste under the Mixed Waste Integrated Program. The status of the technical initiatives in chemical/physical treatment, destruction/stabilization technology, off-gas treatment, and final waste form production/assessment is described in this paper

  16. Development of solid radionuclide waste forms in the United States

    International Nuclear Information System (INIS)

    Crandall, J.L.

    1979-01-01

    New ways of reworking the wastes require a new classification in terms of the final waste forms. This paper surveys the candidate forms: encapsulation binders, in-place solidification waste forms, glass and ceramic waste forms, mineral waste forms, matrix waste forms, gaseous waste forms (fixation), and canisters and engineered barriers. Participants in the US-high-level waste form development program are listed. Requirements and selection of waste forms are also discussed. 26 references

  17. Options for Healthcare Waste Management and Treatment in China

    Institute of Scientific and Technical Information of China (English)

    2006-01-01

    Healthcare waste management and treatment is one of the national priority tasks of China's Tenth Five-Year Plan.Numerous installations disposing medical waste have already operated the project or under construction to the operation in 2006. This paper focuses on the assessment of existing and fu~re options to handle medical waste (MW). Internationally available and so far in China applied technologies and management practice are analysed, including the problems how to materials. Non-hazardous MW can be managed and treated in analogue to municipal solid waste (MSW). In most of the European countries decentralised hospital incinerators have been, because of high operation costs and pollution problems,widely banned and replaced by pre-treatment technologies at the source and centralised incineration plants for hazardous MW.Information for adapting and further developing MW management solutions and treatment technologies in China and applying the most appropriate MWM practice is provided.

  18. Process simulation and uncertainty analysis of plasma arc mixed waste treatment

    International Nuclear Information System (INIS)

    Ferrada, J.J.; Welch, T.D.

    1994-01-01

    Innovative mixed waste treatment subsystems have been analyzed for performance, risk, and life-cycle cost as part of the U.S. Department of Energy's (DOE)'s Mixed Waste Integrated Program (MWIP) treatment alternatives development and evaluation process. This paper concerns the analysis of mixed waste treatment system performance. Performance systems analysis includes approximate material and energy balances and assessments of operability, effectiveness, and reliability. Preliminary material and energy balances of innovative processes have been analyzed using FLOW, an object-oriented, process simulator for waste management systems under development at Oak Ridge National Laboratory. The preliminary models developed for FLOW provide rough order-of-magnitude calculations useful for sensitivity analysis. The insight gained from early modeling of these technologies approximately will ease the transition to more sophisticated simulators as adequate performance and property data become available. Such models are being developed in ASPEN by DOE's Mixed Waste Treatment Project (MWTP) for baseline and alternative flow sheets based on commercial technologies. One alternative to the baseline developed by the MWIP support groups in plasma arc treatment. This process offers a noticeable reduction in the number of process operations as compared to the baseline process because a plasma arc melter is capable of accepting a wide variety of waste streams as direct inputs (without sorting or preprocessing). This innovative process for treating mixed waste replaces several units from the baseline process and, thus, promises an economic advantage. The performance in the plasma arc furnace will directly affect the quality of the waste form and the requirements of the off-gas treatment units. The ultimate objective of MWIP is to reduce the amount of final waste produced, the cost, and the environmental impact

  19. Rib fractures in trauma patients: does operative fixation improve outcome?

    Science.gov (United States)

    Majak, Peter; Næss, Pål A

    2016-12-01

    Renewed interest in surgical fixation of rib fractures has emerged. However, conservative treatment is still preferred at most surgical departments. We wanted to evaluate whether operative treatment of rib fractures may benefit severely injured patients. Several studies report a reduction in mechanical ventilation time, ICU length of stay (LOS), hospital LOS, pneumonia, need for tracheostomy, pain and costs in operatively treated patients with multiple rib fractures compared with patients treated nonoperatively. Although patient selection and timing of the operation seem crucial for successful outcome, no consensus exists. Mortality reduction has only been shown in a few studies. Most studies are retrospective cohort and case-control studies. Only four randomized control trials exist. Conservative treatment, consisting of respiratory assistance and pain control, is still the treatment of choice in the vast majority of patients with multiple rib fractures. In selected patients, operative fixation of fractured ribs within 72 h postinjury may lead to better outcome. More randomized control trials are needed to further determine who benefits from surgical fixation of rib fractures.

  20. Fixation of radioactive waste by reaction with clays: progress report

    International Nuclear Information System (INIS)

    Delegard, C.H.; Barney, G.S.

    1975-07-01

    Reactions of clay with Hanford-type radioactive wastes (liquids, salt cake, and sludge) were studied as a means of immobilization of radionuclides contained in the waste. Products of these reactions were identified as the crystalline sodium aluminosilicates, cancrinite and nepheline. Radionuclides are entrapped in these crystalline minerals. Conceptual flow diagrams for conversion of high-salt wastes to cancrinite and nepheline were defined and tested. The mineral products were evaluated for use as forms for long-term storage of radioactive waste

  1. Mechanical-biological waste treatment and the associated occupational hygiene in Finland

    International Nuclear Information System (INIS)

    Tolvanen, Outi K.; Haenninen, Kari I.

    2006-01-01

    A special feature of waste management in Finland has been the emphasis on the source separation of kitchen biowaste (catering waste); more than two-thirds of the Finnish population participates in this separation. Source-separated biowaste is usually treated by composting. The biowaste of about 5% of the population is handled by mechanical-biological treatment. A waste treatment plant at Mustasaari is the only plant in Finland using digestion for kitchen biowaste. For the protection of their employees, the plant owners commissioned a study on environmental factors and occupational hygiene in the plant area. During 1998-2000 the concentrations of dust, microbes and endotoxins and noise levels were investigated to identify possible problems at the plant. Three different work areas were investigated: the pre-processing and crushing hall, the bioreactor hall and the drying hall. Employees were asked about work-related health problems. Some problems with occupational hygiene were identified: concentrations of microbes and endotoxins may increase to levels harmful to health during waste crushing and in the bioreactor hall. Because employees complained of symptoms such as dry cough and rash or itching appearing once or twice a month, it is advisable to use respirator masks (class P3) during dusty working phases. The noise level in the drying hall exceeded the Finnish threshold value of 85 dBA. Qualitatively harmful factors for the health of employees are similar in all closed waste treatment plants in Finland. Quantitatively, however, the situation at the Mustasaari treatment plant is better than at some Finnish dry waste treatment plants. Therefore is reasonable to conclude that mechanical sorting, which produces a dry waste fraction for combustion and a biowaste fraction for anaerobic treatment, is in terms of occupational hygiene better for employees than combined aerobic treatment and dry waste treatment

  2. Final waste management programmatic environmental impact statement for managing treatment, storage, and disposal of radioactive and hazardous waste. Volume I of V

    International Nuclear Information System (INIS)

    1997-05-01

    The Final Waste Management Programmatic Environmental Impact Statement (WM PEIS) examines the potential environmental and cost impacts of strategic management alternatives for managing five types of radioactive and hazardous wastes that have resulted and will continue to result from nuclear defense and research activities at a variety of sites around the United States. The five waste types are low-level mixed waste, low-level waste, transuranic waste, high-level waste, and hazardous waste. The WM PEIS provides information on the impacts of various siting alternatives which the Department of Energy (DOE) will use to decide at which sites to locate additional treatment, storage, and disposal capacity for each waste type. This information includes the cumulative impacts of combining future siting configurations for the five waste types and the collective impacts of other past, present, and reasonably foreseeable future activities. The selected waste management facilities being considered for these different waste types are treatment and disposal facilities for low-level mixed waste; treatment and disposal facilities for low-level waste; treatment and storage facilities for transuranic waste in the event that treatment is required before disposal; storage facilities for treated (vitrified) high-level waste canisters; and treatment of nonwastewater hazardous waste by DOE and commercial vendors. In addition to the no action alternative, which includes only existing or approved waste management facilities, the alternatives for each of the waste type configurations include decentralized, regionalized, and centralized alternatives for using existing and operating new waste management facilities. However, the siting, construction and operations of any new facility at a selected site will not be decided until completion of a sitewide or project-specific environmental impact review

  3. Handling and Treatment of Poultry Hatchery Waste: A Review

    Directory of Open Access Journals (Sweden)

    Belinda Rodda

    2011-01-01

    Full Text Available A literature review was undertaken to identify methods being used to handle and treat hatchery waste. Hatchery waste can be separated into solid waste and liquid waste by centrifuging or by using screens. Potential methods for treating hatchery waste on site include use of a furnace to heat the waste to produce steam to run a turbine generator or to use an in line composter to stabilise the waste. There is also potential to use anaerobic digestion at hatcheries to produce methane and fertilisers. Hatcheries disposing wastewater into lagoons could establish a series of ponds where algae, zooplankton and fish utilise the nutrients using integrated aquaculture which cleans the water making it more suitable for irrigation. The ideal system to establish in a hatchery would be to incorporate separation and handling equipment to separate waste into its various components for further treatment. This would save disposal costs, produce biogas to reduce power costs at plants and produce a range of value added products. However the scale of operations at many hatcheries is too small and development of treatment systems may not be viable.

  4. Hong kong chemical waste treatment facilities: a technology overview

    Energy Technology Data Exchange (ETDEWEB)

    Siuwang, Chu [Enviropace Ltd., Hong Kong (Hong Kong)

    1994-12-31

    The effective management of chemical and industrial wastes represents one of the most pressing environmental problems confronting the Hong Kong community. In 1990, the Hong Kong government contracted Enviropace Limited for the design, construction and operation of a Chemical Waste Treatment Facility. The treatment and disposal processes, their integration and management are the subject of discussion in this paper

  5. Hong kong chemical waste treatment facilities: a technology overview

    Energy Technology Data Exchange (ETDEWEB)

    Siuwang, Chu [Enviropace Ltd., Hong Kong (Hong Kong)

    1993-12-31

    The effective management of chemical and industrial wastes represents one of the most pressing environmental problems confronting the Hong Kong community. In 1990, the Hong Kong government contracted Enviropace Limited for the design, construction and operation of a Chemical Waste Treatment Facility. The treatment and disposal processes, their integration and management are the subject of discussion in this paper

  6. Treatment and disposal techniques of dangerous municipal solid wastes

    International Nuclear Information System (INIS)

    Beone, G.; Carbone, A.I.; Zagaroli, M.

    1989-01-01

    This paper describes the qualitative and quantitative features of the different types of dangerous municipal solid wastes, according to Italian law. In the second part the impact on environment and man health is presented. This impact should be minimized by suitable controlled disposal techniques, which differ from other municipal waste treatments. Finally, the paper deals with the most appropriate systems for treatment and disposal of such kind of waste. Particularly, some research activities in the field of metal recovery from used batteries, sponsored by ENEA, and carrying out by private companies, are described. (author)

  7. [Treatment of open tile type C pelvic fractures by open reduction and internal fixation through anterior and posterior approaches at early stage].

    Science.gov (United States)

    Li, Baichuan

    2014-05-01

    To explore the effectiveness of open reduction and internal fixation through anterior and posterior approaches in treatment of open Tile type C pelvic fractures at early stage. Between January 2009 and April 2012, 12 patients with open Tile C pelvic fractures were treated. There were 7 males and 5 females, aged 6-53 years (median, 31 years). Of 12 cases, 4 were classified as Tile type C1, 6 as Tile type C2, and 2 as Tile type C3; 5 were rated as Gustilo type II and 7 as Gustilo type III. The injury severity score was 18-57 (mean, 37.2). The interval of injury and admission ranged from 15 minutes to 3 days (median, 50 minutes). The debridement and external fixation were performed at first stage; then open reduction and internal fixation were used through anterior approach (reconstruction plate) and posterior approach (cannulated lag screws). The vacuum sealing drainage was performed during treatment until the wounds healed. Delayed healing of incison was obtained in 12 cases because of wound infection. Anatomical reduction or approximate anatomical reduction was achieved in all 12 cases. The patients were followed up 3-39 months (median, 18 months). No loosening of internal fixation or fracture displacement was observed during follow-up. The fracture healing time was 7-13 weeks (mean, 9.7 weeks). At last follow-up, according to the Matta standard, the outcome was excellent in 10 cases and good in 2 cases; according to Majeed score, the results were excellent in 9 cases, good in 1, and poor in 2. Early internal fixation operation of open Tile type C pelvic fractures can effectively restore the pelvic anatomical structure and stability, reduce the complication, and achieve satisfactory effectiveness.

  8. Removal of internal fixation--the effect on patients' complaints: a study of 66 cases of removal of internal fixation after malleolar fractures

    DEFF Research Database (Denmark)

    Jacobsen, S; Honnens de Lichtenberg, M; Jensen, C M

    1994-01-01

    To estimate the effect of removal of internal fixation after treatment of malleolar fractures on postoperatively presented complaints, we retrospectively evaluated 66 patients by their records and by personal questionnaires. Of all the patients, 89.4% had one or more complaints. These were...... typically soreness over implant and cicatrix, reduced movement of the ankle joint, and strain-related pain. About 75% of these patients reported improvement after removal. The AO mode of fixation, i.e., typically by lateral semitubular plating and transsyndesmotic screw and a medial screw or pins...... period. We conclude that removal of internal fixation after malleolar fractures is indicated when common types of complaints are presented....

  9. Membrane preparation and process development for radioactive waste treatment

    Energy Technology Data Exchange (ETDEWEB)

    Lee, K. W.; Kim, G. W.; Kim, S. K. [KAERI, Daejeon (Korea, Republic of); and others

    2012-01-15

    The membrane manufacturing technology with hydrophilic function that can minimize fouling when it applies to the radioactive liquid waste treatment process was developed. Thermodynamic and rheological analysis for polysulfone casting solution containing polyvinylpyrrolidone was performed. On the basis of the results of preparation of the hydrophilic polymer membrane solution, the hollow fiber membrane for radioactive liquid waste treatment was manufactured and its performance analysis was carried out. As a results, it turns out the hydrophilic hollow fiber membrane has more 90 % of flux increment effect and also more 2.5 times fouling reducing effect than one prepared with only polysulfone. In addition, as investigating the separation property of radioactive liquid waste for the electrofilteration membrane process, a proper range for application of radioactive liquid wastes was established through the thorough electrofiltration analysis of various wastes containing metal salt, surfactants and oil.

  10. Membrane preparation and process development for radioactive waste treatment

    International Nuclear Information System (INIS)

    Lee, K. W.; Kim, G. W.; Kim, S. K.

    2012-01-01

    The membrane manufacturing technology with hydrophilic function that can minimize fouling when it applies to the radioactive liquid waste treatment process was developed. Thermodynamic and rheological analysis for polysulfone casting solution containing polyvinylpyrrolidone was performed. On the basis of the results of preparation of the hydrophilic polymer membrane solution, the hollow fiber membrane for radioactive liquid waste treatment was manufactured and its performance analysis was carried out. As a results, it turns out the hydrophilic hollow fiber membrane has more 90 % of flux increment effect and also more 2.5 times fouling reducing effect than one prepared with only polysulfone. In addition, as investigating the separation property of radioactive liquid waste for the electrofilteration membrane process, a proper range for application of radioactive liquid wastes was established through the thorough electrofiltration analysis of various wastes containing metal salt, surfactants and oil

  11. Liquid waste treatment at plutonium fuels fabrication facility, 2

    International Nuclear Information System (INIS)

    Matsumoto, Ken-ichi; Itoh, Ichiroh; Ohuchi, Jin; Miyo, Hiroaki

    1974-01-01

    The economics in the management of the radioactive liquid waste from Plutonium Fuels Fabrication Facility with sludge-blanket type flocculators has been evaluated. (1) Cost calculation: The cost of chemicals and electricity to treat 1 cubic meter of liquid waste is about 876 yen, while the total operating cost is 250 thousand yen per cubic meter in the case of 140 m 3 /year treatment. These figures are much higher than those for ordinary wastes, due to the particular operation against plutonium. (2) Proposal of the closed system for liquid waste treatment at PFFF: In the case of a closed system using evaporator, ion exchange column and rotary-kiln calciner, the operating cost is estimated at 40 thousand yen per cubic meter of liquid waste. Final radioactivity of treated liquid is below 10 -8 micro curies/ml. (Mori, K.)

  12. Mixed and low-level waste treatment facility project

    International Nuclear Information System (INIS)

    1992-04-01

    The technology information provided in this report is only the first step toward the identification and selection of process systems that may be recommended for a proposed mixed and low-level waste treatment facility. More specific information on each technology will be required to conduct the system and equipment tradeoff studies that will follow these preengineering studies. For example, capacity, maintainability, reliability, cost, applicability to specific waste streams, and technology availability must be further defined. This report does not currently contain all needed information; however, all major technologies considered to be potentially applicable to the treatment of mixed and low-level waste are identified and described herein. Future reports will seek to improve the depth of information on technologies

  13. Mixed and low-level waste treatment facility project

    Energy Technology Data Exchange (ETDEWEB)

    1992-04-01

    The technology information provided in this report is only the first step toward the identification and selection of process systems that may be recommended for a proposed mixed and low-level waste treatment facility. More specific information on each technology will be required to conduct the system and equipment tradeoff studies that will follow these preengineering studies. For example, capacity, maintainability, reliability, cost, applicability to specific waste streams, and technology availability must be further defined. This report does not currently contain all needed information; however, all major technologies considered to be potentially applicable to the treatment of mixed and low-level waste are identified and described herein. Future reports will seek to improve the depth of information on technologies.

  14. Risk assessment of CST-7 proposed waste treatment and storage facilities Volume I: Limited-scope probabilistic risk assessment (PRA) of proposed CST-7 waste treatment ampersand storage facilities. Volume II: Preliminary hazards analysis of proposed CST-7 waste storage ampersand treatment facilities

    International Nuclear Information System (INIS)

    Sasser, K.

    1994-06-01

    In FY 1993, the Los Alamos National Laboratory Waste Management Group [CST-7 (formerly EM-7)] requested the Probabilistic Risk and Hazards Analysis Group [TSA-11 (formerly N-6)] to conduct a study of the hazards associated with several CST-7 facilities. Among these facilities are the Hazardous Waste Treatment Facility (HWTF), the HWTF Drum Storage Building (DSB), and the Mixed Waste Receiving and Storage Facility (MWRSF), which are proposed for construction beginning in 1996. These facilities are needed to upgrade the Laboratory's storage capability for hazardous and mixed wastes and to provide treatment capabilities for wastes in cases where offsite treatment is not available or desirable. These facilities will assist Los Alamos in complying with federal and state requlations

  15. The environmental impact of mine wastes - roles of microorganisms and their significance in treatment of mine wastes

    International Nuclear Information System (INIS)

    Ledin, M.; Pedersen, K.

    1996-01-01

    Mine wastes constitute a potential source of contamination to the environment, as heavy metals and acid are released in large amounts. A great variety of microorganisms has been found in mine wastes and microbiological processes are usually responsible for the environmental hazard created by mine wastes. However, microorganisms can also be used to retard the adverse impact of mine wastes on the environment. Conventionally, the mine drainage as well as the waste itself can be treated with alkali to increase pH and precipitate metals. The main drawback of this method is that it has to be continuously repeated to be fully effective. There may also be negative effects on beneficial microorganisms. Several other treatment methods have been developed to stop weathering processes thereby reducing the environmental impact of mine wastes. The other main approach is to treat the drainage water. Various methods aim at using microorganisms for this in natural or engineered systems. Recently, much interest has been focused on the use of natural or artificial wetlands for treatment. In general, the activity of microorganisms is neglected in the design of mine waste treatment systems, and the treatments are created merely from a technical point of view. This can result in situations where unexpected microbial processes take over, and, in the worst scenario, the overall effect is opposite to the desired

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

    International Nuclear Information System (INIS)

    2007-01-01

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

  17. Initial Selection of Supplemental Treatment Technologies for Hanford's Low-Activity Tank Waste

    International Nuclear Information System (INIS)

    Raymond, Richard E.; Powell, Roger W.; Hamilton, Dennis W.; Kitchen, William A.; Mauss, Billie M.; Brouns, Thomas M.

    2004-01-01

    In 2002, the U.S. Department of Energy (DOE) documented a plan for accelerating cleanup of the Hanford Site, located in southeastern Washington State, by at least 35 years (DOE 2002). A key element of the accelerated cleanup plan was a strategic initiative for acceleration of the tank waste program and completion of ''tank waste treatment by 2028 by increasing the capacity of the planned Waste Treatment Plant (ETP) and using supplemental technologies for waste treatment and immobilization''. The plan identified specific technologies to be evaluated for supplemental treatment of as much as 70% of the low-activity waste (LAW). The objective was to complete required testing and evaluation that would ''...bring an appropriate combination of the above technologies to deployment to supplement LAW treatment and immobilization in the WTP to achieve the completion of tank waste treatment by 2028''. In concert with this acceleration plan, DOE, the U.S. Environmental Protection Agency, and the Washington State Department of Ecology have proposed to accelerate from 2012 to 2005 the Hanford Federal Facility Compliance Agreement (Tri-Party Agreement) milestone (M-62-08) associated with a final decision on treatment of the balance of tank waste that is beyond the capacity of the currently designed WTP

  18. REVISION ANKLE SYNDESMOSIS FIXATION - FUNCTIONAL OUTCOME AFTER TIGHTROPE ® FIXATION

    Directory of Open Access Journals (Sweden)

    Sendhilvelan Rajagopalan

    2016-07-01

    Full Text Available BACKGROUND Syndesmotic disruptions are often seen in ankle fractures. Malreduction of these fractures can result in arthritis and instability. A proportion of these patients with malreduction require revision fixation. This study presents the results of revision fixation in such patients, using the Ankle TightRope ® (Arthrex system. METHODS Between January 2000 to December 2009, 124 patients who underwent ankle fracture fixations with syndesmotic stabilisation were analysed. Out of 124 patients, 8 patients were diagnosed with failure of primary stabilisation (based on radiological and clinical criteria and subjected to revision fixation using the Ankle TightRope ® (Arthrex system. Followup was done at periodic time intervals of 3, 6 and 12 months. Both clinical and radiological assessment was performed. Complications and duration of hospital stay was recorded. Functional evaluation was performed using the American Orthopaedic Foot and Ankle Society (AOFAS scoring system. RESULTS Five patients had good results, one satisfactory and two had poor outcomes. CONCLUSIONS Ankle TightRope ® fixation is an alternative method of stabilisation in patients who require revision syndesmosis fixation. Further studies are required to evaluate this method of revision stabilisation as compared to screws.

  19. Production of metal waste forms from spent fuel treatment

    International Nuclear Information System (INIS)

    Westphal, B.R.; Keiser, D.D.; Rigg, R.H.; Laug, D.V.

    1995-01-01

    Treatment of spent nuclear fuel at Argonne National Laboratory consists of a pyroprocessing scheme in which the development of suitable waste forms is being advanced. Of the two waste forms being proposed, metal and mineral, the production of the metal waste form utilizes induction melting to stabilize the waste product. Alloying of metallic nuclear materials by induction melting has long been an Argonne strength and thus, the transition to metallic waste processing seems compatible. A test program is being initiated to coalesce the production of the metal waste forms with current induction melting capabilities

  20. Evaluation of waste disposal by shale fracturing

    International Nuclear Information System (INIS)

    Weeren, H.O.

    1976-02-01

    The shale fracturing process is evaluated as a means for permanent disposal of radioactive intermediate level liquid waste generated at the Oak Ridge National Laboratory. The estimated capital operating and development costs of a proposed disposal facility are compared with equivalent estimated costs for alternative methods of waste fixation

  1. In Situ Modular Waste Retrieval and Treatment System

    International Nuclear Information System (INIS)

    Walker, M.S.

    1996-10-01

    As part of the Comprehensive Environmental Response, Compensation, and Liability Act process from remediation of Waste Area Grouping (WAG 6) at ORNL, a public meeting was held for the Proposed Plan. It was recognized that contaminant releases from WAG 6 posed minimal potential risk to the public and the environment. The US DOE in conjunction with the US EPA and the TDEC agreed to defer remedial action at WAG 6 until higher risk release sites were first remediated. This report presents the results of a conceptual design for an In Situ Modular Retrieval and Treatment System able to excavate, shred, and process buried waste on site, with minimum disturbance and distribution of dust and debris. the system would bring appropriate levels of treatment to the waste then encapsulate and leave it in place. The system would be applicable to areas in which waste was disposed in long trenches

  2. Hanford Tank Waste Treatment and Immobilization Plant (WTP) Waste Feed Qualification Program Development Approach - 13114

    Energy Technology Data Exchange (ETDEWEB)

    Markillie, Jeffrey R.; Arakali, Aruna V.; Benson, Peter A.; Halverson, Thomas G. [Hanford Tank Waste Treatment and Immobilization Plant Project, Richland, WA 99354 (United States); Adamson, Duane J.; Herman, Connie C.; Peeler, David K. [Savannah River National Laboratory, Aiken, SC 29808 (United States)

    2013-07-01

    The Hanford Tank Waste Treatment and Immobilization Plant (WTP) is a nuclear waste treatment facility being designed and constructed for the U.S. Department of Energy by Bechtel National, Inc. and subcontractor URS Corporation (under contract DE-AC27-01RV14136 [1]) to process and vitrify radioactive waste that is currently stored in underground tanks at the Hanford Site. A wide range of planning is in progress to prepare for safe start-up, commissioning, and operation. The waste feed qualification program is being developed to protect the WTP design, safety basis, and technical basis by assuring acceptance requirements can be met before the transfer of waste. The WTP Project has partnered with Savannah River National Laboratory to develop the waste feed qualification program. The results of waste feed qualification activities will be implemented using a batch processing methodology, and will establish an acceptable range of operator controllable parameters needed to treat the staged waste. Waste feed qualification program development is being implemented in three separate phases. Phase 1 required identification of analytical methods and gaps. This activity has been completed, and provides the foundation for a technically defensible approach for waste feed qualification. Phase 2 of the program development is in progress. The activities in this phase include the closure of analytical methodology gaps identified during Phase 1, design and fabrication of laboratory-scale test apparatus, and determination of the waste feed qualification sample volume. Phase 3 will demonstrate waste feed qualification testing in support of Cold Commissioning. (authors)

  3. Treatment of reducible unstable fractures of the distal radius: randomized clinical study comparing the locked volar plate and external fixator methods: study protocol.

    Science.gov (United States)

    Raduan Neto, Jorge; de Moraes, Vinicius Ynoe; Gomes Dos Santos, João B; Faloppa, Flávio; Belloti, João Carlos

    2014-03-05

    Various treatments are available for reducible unstable fractures of the distal radius, such as closed reduction combined with fixation by external fixator (EF), and rigid internal fixation using a locked volar plate (VP). Although there are studies comparing these methods, there is no conclusive evidence indicating which treatment is best. The hypothesis of this study is that surgical treatment with a VP is more effective than EF from the standpoint of functional outcome (patient-reported). The study is randomized clinical trial with parallel groups and a blinded evaluator and involves the surgical interventions EF and VP. Patients will be randomly assigned (assignment ratio 1:1) using sealed opaque envelopes. This trial will include consecutive adult patients with an acute (up to 15 days) displaced, unstable fracture of the distal end of the radius of type A2, A3, C1, C2 or C3 by the Arbeitsgemeinschaft für Osteosynthesefragen-Association for the Study of Internal Fixation classification and type II or type III by the IDEAL32 classification, without previous surgical treatments of the wrist. The surgical intervention assigned will be performed by three surgical specialists familiar with the techniques described. Evaluations will be performed at 2, and 8 weeks, 3, 6 and 12 months, with the primary outcomes being measured by the Disabilities of the Arm, Shoulder and Hand (DASH) questionnaire and measurement of pain (Visual Analog Pain Scale and digital algometer). Secondary outcomes will include radiographic parameters, objective functional evaluation (goniometry and dynamometry), and the rate of complications and method failure according to the intention-to-treat principle. Final postoperative evaluations (6 and 12 months) will be performed by independent blinded evaluators. For the Student's t-test, a difference of 10 points in the DASH score, with a 95% confidence interval, a statistical power of 80%, and 20% sampling error results in 36 patients per group

  4. Nuclear waste management. Quarterly progress report, October-December 1979

    Energy Technology Data Exchange (ETDEWEB)

    Platt, A.M.; Powell, J.A. (comps.)

    1980-04-01

    Progress and activities are reported on the following: high-level waste immobilization, alternative waste forms, nuclear waste materials characterization, TRU waste immobilization programs, TRU waste decontamination, krypton solidification, thermal outgassing, iodine-129 fixation, monitoring of unsaturated zone transport, well-logging instrumentation development, mobile organic complexes of fission products, waste management system and safety studies, assessment of effectiveness of geologic isolation systems, waste/rock interactions technology, spent fuel and fuel pool integrity program, and engineered barriers. (DLC)

  5. Calculation of Hazardous Waste Land Disposal Restrictions (LDR) Treatment Standards

    Science.gov (United States)

    examples of calculations of treatment standards including for High Concentration Selenium Wastes Using Data Submitted by Chemical Waste Management (CWM) and Antimony Using Data Submitted by Chemical Waste Management and Data Obtained From Rollins.

  6. Final waste management programmatic environmental impact statement for managing treatment, storage, and disposal of radioactive and hazardous waste. Volume V of V

    International Nuclear Information System (INIS)

    1997-01-01

    The Final Waste Management Programmatic Environmental Impact Statement (WM PEIS) examines the potential environmental and cost impacts of strategic management alternatives for managing five types of radioactive and hazardous wastes that have resulted and will continue to result from nuclear energy research and the development, production, and testing of nuclear weapons at a variety of sites around the United States. The five waste types are low-level mixed waste, low-level waste, transuranic waste, high-level waste, and hazardous waste. The WM PEIS provides information on the impacts of various siting alternatives, which the Department of Energy (DOE) will use to decide at which sites to locate additional treatment, storage, and disposal capacity for each waste type. This information includes the cumulative impacts of combining future siting configurations for the five waste types and the collective impacts of other past, present, and reasonably foreseeable future activities. The selected waste management facilities being considered for these different waste types are treatment and disposal facilities for low-level mixed waste; treatment and disposal facilities for low-level waste; treatment and storage facilities for transuranic waste in the event that treatment is required before disposal; storage facilities for created (vitrified) high-level waste canisters; and treatment of nonwastewater hazardous waste by DOE and commercial vendors. In addition to the No Action Alternative, which includes only existing of approved waste management facilities, the alternatives for each of the waste-type configurations include Decentralized, Regionalized, and Centralized Alternatives for using existing and operating new waste management facilities. However, the siting, construction, and operations of any new facility at a selected site will not be decided until completion of a sitewide or project-specific environmental impact review

  7. Fixation of Soil Using PEC and Separation of Fixed Soil

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Yong Suk; Yang, Hee-Man; Lee, Kune Woo; Seo, Bum-Kyoung; Moon, Jei Kwon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-10-15

    Radioactive cesium (Cs-137) is the most apprehensive element due to its long half-lives, high solubility in water, and strong radiation emission in the form of gamma rays. Because the radioactivity is localized within topsoil, soil surface on topsoil should be fixed to prevent the spreading of the contaminated soils by wind and water erosion. Many methods have been developing for soil fixation to remove radioactive contaminants in soil and prevent to diffuse radioactive materials. Various materials have been used as fixatives such as clays, molecular sieves, polymer, and petroleum based products. One of the methods is a soil fixation or solidification using polyelectrolyte. Polyelectrolytes have many ionic groups and form the polyelectrolyte complex (PEC) due to electrostatic interaction of anion and cation in an aqueous solution. polyelectrolyte complex can fix soil particles by flocculation and formation of crust between soil. The method can prevent a spread of radioactive material by floating on a soil surface. The decontamination efficiency of the surface soils reached about 90%, and dust release was effectively suppressed during the removal of surface soils. However it has a problem that the removed soil must separate soil and polymer to treat as the waste. In this study, the fixation of soil by polyelectrolyte complex to suppress the spread of contaminant and the separation method of soil and polymer was investigated. The properties of polyelectrolyte complex solution and the stability of fixed soil by polyelectrolyte complex were investigated. The concentration of salt in the polyelectrolyte complex solution is a very important parameter for the soil fixation.

  8. Treatment of mixed wastes by thermal plasma discharges

    International Nuclear Information System (INIS)

    Diaz A, L.V.

    2007-01-01

    The present study has as purpose to apply the technology of thermal plasma in the destruction of certain type of waste generated in the ININ. As first instance, origin, classification and disposition of the radioactive waste generated in the ININ is identified. Once identified the waste, the waste to treat is determined based on: the easiness of treating him with plasma, classification and importance. Later on, a substance or compound settles down (sample model) that serves as indicative of the waste for its physical-chemical characteristics, this is made because in the Thermal Plasma Applications Laboratory is not had the license to work with radioactive material. The sample model and the material to form the vitreous matrix are characterized before and after the treatment in order to evaluating their degradation and vitrification. During the treatment by means of the thermal plasma, the appropriate conditions are determined for the degradation and vitrification of the waste. Also, it is carried out an energy balance in the system to know the capacity to fuse the material depending the transfer of existent heat between the plasma and the material to treat. Obtaining favorable results, it thought about to climb in the project and by this way to help to solve one of the environmental problems in Mexico, as they are it the mixed wastes. (Author)

  9. Application of macrophytes as biosorbents for radioactive liquid waste treatment

    International Nuclear Information System (INIS)

    Vieira, Ludmila Cabreira

    2016-01-01

    Radioactive waste as any other type of waste should be treated and disposed adequately. It is necessary to consider its physical, chemical and radiological characteristics for choosing the appropriate action for the treatment and final disposal. Many treatment techniques currently used are economically costly, often invalidating its use and favoring the study of other treatment techniques. One of these techniques is biosorption, which demonstrates high potential when applied to radioactive waste. This technology uses materials of biological origin for removing metals. Among potential biosorbents found, macrophyte aquatics are useful because they may remove uranium present in the liquid radioactive waste at low cost. This study aims to evaluate the biosorption capacity of macrophyte aquatics Pistia stratiotes, Limnobium laevigatum, Lemna sp and Azolla sp in the treatment of liquid radioactive waste. This study was divided into two stages, the first one is characterization and preparation of biosorption and the other is tests, carried out with uranium solutions and real samples. The biomass was tested in its raw form and biosorption assays were performed in polypropylene vials containing 10 ml of solution of uranium or 10ml of radioactive waste and 0.20g of biomass. The behavior of biomass was evaluated by sorption kinetics and isotherm models. The highest sorption capacities found was 162.1 mg / g for the macrophyte Lemna sp and 161.8 mg / g for the Azolla sp. The equilibrium times obtained were 1 hour for Lemna sp, and 30 minutes for Azolla sp. With the real waste, the macrophyte Azolla sp presented a sorption capacity of 2.6 mg / g. These results suggest that Azolla sp has a larger capacity of biosorption, therefore it is more suitable for more detailed studies of treatment of liquid radioactive waste. (author)

  10. Mixed Waste Treatment Using the ChemChar Thermolytic Detoxification Technique

    International Nuclear Information System (INIS)

    Kuchynka, D.J.

    1997-01-01

    This R and D program addresses the treatment of mixed waste employing the ChemChar Thermolytic Detoxification process. Surrogate mixed waste streams will be treated in a four inch diameter, continuous feed, adiabatic reactor with the goal of meeting all regulatory treatment levels for the contaminants in the surrogates with the concomitant production of contaminant free by-products. Successful completion of this program will show that organic contaminants in mixed waste surrogates will be converted to a clean, energy rich synthesis gas capable of being used, without further processing, for power or heat generation. The inorganic components in the surrogates will be found to be adsorbed on a macroporous coal char activated carbon substrate which is mixed with the waste prior to treatment. These contaminants include radioactive metal surrogate species, RCRA hazardous metals and any acid gases formed during the treatment process. The program has three main tasks that will be performed to meet the above objectives. The first task is the design and construction of the four inch reactor at Mirage Systems in Sunnyvale, CA. The second task is production and procurement of the activated carbon char employed in the ChemChartest runs and identification of two surrogate mixed wastes. The last task is testing and operation of the reactor on char/surrogate waste mixtures to be performed at the University of Missouri. The deliverables for the project are a Design Review Report, Operational Test Plan, Topical Report and Final Report. This report contains only the results of the design and construction carbon production-surrogate waste identification tasks.Treatment of the surrogate mixed wastes has just begun and will not be reported in this version of the Final Report. The latter will be reported in the final version of the Final Report

  11. [Manipulative reduction and small splint fixation combined with micromovement exercise for treatment of humeral shaft fractures].

    Science.gov (United States)

    Tang, Hao-chen; Xiang, Ming; Chen, Hang; Hu, Xiao-chuan; Yang, Guo-yong

    2016-01-01

    To investigate the therapeutic efficacy of bone-setting manipulative reduction and small splint fixation combined with micro-movement theory exercise for treatment of humeral shaft fractures. From March 2011 to February 2014, 64 cases of humeral shaft fractures were treated by bone-setting manipulative reduction and small splint fixation including 28 males and 36 females with an average age of 38.1 years old ranging from 22 to 67 years old. According to the classification of AO/OTA, there were 10 cases of type A1, 12 cases of type A2,11 cases of type A3,10 cases of type B1,12 cases of type B2, 7 cases of type B3, 2 cases of type C1, 1 case of type C2, 1 case of type C3. After close reduction early functional exercise performed according to micro-movement theory. All patients had no other parts of the fractures, neurovascular injury, and serious medical problems. Patients were followed up for fracture healing, shoulder and elbow joint function recovery, and curative effect. All patients were followed up from 10 to 12 months with an average of 10.3 months. Of them, 2 cases had a small amount of callus growth at 3 months after close reduction, so instead of operation; 2 cases appeared radial nerve symptoms after close reduction ,so instead of operation. Other patients were osseous healing, the time was 8 to 12 weeks with an average of 10.2 weeks. After osseous healing, according to Constant-Murley score system ,the average score was (93.5 ± 3.2) points, the result was excellent in 29 cases, good in 29 cases, fair in 6 cases, excellent and good rate was 90.3%; according to the Mayo score system, the average score was (93.7 ± 4.2) points, the result was excellent in 35 cases, good in 23 cases, fair in 6 cases, excellent and good rate was 91.9%. Bone-setting manipulative reduction and small splint fixation combined with micromovement theory exercise for treatment of humeral shaft fractures has advantage of positive effect, easy and inexpensive method, the treatment has

  12. Waste treatment using molten salt oxidation

    International Nuclear Information System (INIS)

    Navratil, J.D.; Stewart, A.E.

    1996-01-01

    MSO technology can be characterized as a submerged oxidation process; the basic concept is to introduce air and wastes into a bed of molten salt, oxidize the organic wastes in the molten salt, use the heat of oxidation to keep the salt molten and remove the salt for disposal or processing and recycling. The molten salt (usually sodium carbonate at 900-1000 C) provides four waste management functions: providing a heat transfer medium, catalyzing the oxidation reaction, preventing the formation of acid gases by forming stable salts, and efficiently capturing ash particles and radioactive materials by the combined effects of wetting, encapsulation and dissolution. The MSO process requires no wet scrubbing system for off-gas treatment. The process has been developed through bench-scale and pilot-scale testing, with successful destruction demonstration of a wide variety of hazardous and mixed (radioactive and hazardous wastes). (author). 24 refs, 2 tabs, 2 figs

  13. Nuclear waste management. Quarterly progress report, July-September 1980

    Energy Technology Data Exchange (ETDEWEB)

    Chikalla, T.D.

    1980-11-01

    Research is reported on: high-level waste immobilization, alternative waste forms, TRU waste immobilization and decontamination, krypton solidification, thermal outgassing, /sup 129/I fixation, unsaturated zone transport, well-logging instrumentation, waste management system and safety studies, effectiveness of geologic isolation systems, waste/rock interactions, engineered barriers, backfill material, spent fuel storage (criticality), barrier sealing and liners for U mill tailings, and revegetation of inactive U tailings sites. (DLC)

  14. Training manual for process operation and management of radioactive waste treatment facility

    Energy Technology Data Exchange (ETDEWEB)

    Shon, J. S.; Kim, K. J.; Ahn, S. J. [and others

    2004-12-01

    Radioactive Waste Treatment Facility (RWTF) has been operating for safe and effective treatment of radioactive wastes generated in the Korea Atomic Energy Research Institute (KAERI). In RWTF, there are evaporation, bituminization and solar evaporation processes for liquid waste, solid waste treatment process and laundry process. As other radioactive waste treatment facilities in foreign countries, the emergency situation such as fire and overflow of liquid waste can be taken place during the operation and result in the spread of contamination of radioactivity. So, easy and definite operating procedure is necessary for the safe operation of the facility. This manual can be available as easy and concise training materials for new employees and workers dispatched from service agency. Especially, in case of emergency urgently occurred during operation, everyone working in the facility can quickly stop the facility following this procedure.

  15. Training manual for process operation and management of radioactive waste treatment facility

    International Nuclear Information System (INIS)

    Shon, J. S.; Kim, K. J.; Ahn, S. J.

    2004-12-01

    Radioactive Waste Treatment Facility (RWTF) has been operating for safe and effective treatment of radioactive wastes generated in the Korea Atomic Energy Research Institute (KAERI). In RWTF, there are evaporation, bituminization and solar evaporation processes for liquid waste, solid waste treatment process and laundry process. As other radioactive waste treatment facilities in foreign countries, the emergency situation such as fire and overflow of liquid waste can be taken place during the operation and result in the spread of contamination of radioactivity. So, easy and definite operating procedure is necessary for the safe operation of the facility. This manual can be available as easy and concise training materials for new employees and workers dispatched from service agency. Especially, in case of emergency urgently occurred during operation, everyone working in the facility can quickly stop the facility following this procedure

  16. Mixed waste: The treatment of organic radioactive waste by means of adsorbents

    International Nuclear Information System (INIS)

    Sanhueza-Mir, A.; Morales-Galarce, T.

    2001-01-01

    Full text: The work described in this paper has been carried in the radioactive waste treatment facilities of the Nuclear Research Center Lo Aguirre, CEN LA, which are operated by Radioactive Waste Management Unit, UGDR. This last, centralizes its activities in order to manage all radioactive waste generated in the country due to the nuclear development. Features of danger and risks presented by organic radioactive liquid waste, make the need to develop a practicable alternative for its treatment and to allow the conditioning towards a suitable final disposal The raw material for this work, is an organic liquid waste arising from scintillation techniques, contaminated with Tritium. This mixed waste has to be treated and then conditioned in a solid form within a 200 I container, according with actual acceptance criteria for our temporary store for radioactive waste. The best formulation which allows to immobilize the liquid waste was determined. The first step consists in the adsorption treatment that waste is humbled. From the available adsorbents, two types were studied: adsorption granulat and diatomaceous earth. From the waste management standpoint, results with diatomaceous earth present physical characteristics better than the other Following, the second stage is the immobilization, which is achieved in a cement matrix made with puzzolanic cement (Polpaico 400) made in Chile. Later, due to cost and availability in the country, the diatomaceous earth is selected for the study, in the form of celite which is comparatively economic. The best mixture, with regard to physical feature, has the following composition: a 0.35 (w/w) water/cement ratio, which represents the needed quantity to obtain workability in the mixture, and it is the minimum amount of water to hydrating the cement; a waste/adsorbent ratio of 0.5 (v/v), in which the organic liquid is completely adsorbed and it is incorporated into the crystalline system of the solid form; and an adsorbed waste

  17. Impact of decontamination on LWR radioactive waste treatment systems

    International Nuclear Information System (INIS)

    Hoenes, G.R.; Perrigo, L.D.; Divine, J.R.; Faust, L.G.

    1979-01-01

    Only at N-Reactor is there a means to accommodate radwaste produced during decontamination. The Dresden system is expected to be ready to accommodate such solutions by the summer of 1979. Solidification of the processed decontamination waste may be a significant problem. There is doubt that the materials in current radwaste treatment systems can handle chemicals from a concentrated process. The total storage volume, for concentrated decontamination, is not sufficient in existing radwaste treatment systems. Greater attention should be placed on designing reactors and radwaste treatment systems for decontamination. A means of handling waste material resulting from leaks in the primary system during the decontamination must be developed. On-site storage of solidified decontamination wastes may be a viable option, but license amendments will be necessary

  18. Recovery of zinc in phosphor wastes via electrokinetic treatments

    International Nuclear Information System (INIS)

    Yu, M.Y.; Wang, H. Paul; Chen, C.Y.; Hsiung, T.-L.; Wei, Yu-Ling; Tai, H.-S.; Chiang, K.-C.

    2007-01-01

    Speciation of zinc in phosphor wastes during electrokinetic treatments has been studied by in situ X-ray absorption near edge structure (XANES) spectroscopy in the present work. The least-square fits of the in situ XANES spectra show that the major zinc species in the phosphor waste are ZnS (77%), ZnO (10%), and Zn(OH) 2 (13%). During the electrokinetic treatment for 90 min, 25% of ZnS and 4% of ZnO are dissolved. About 42% of zinc is enriched on the cathode under the electric field (5 V/cm). Prolonging the electrokinetic treatment time to 4 h under the electric field of 5 V/cm, at least 80% of zinc in the phosphor waste can be recovered

  19. Non-Thermal Treatment of Hanford Site Low-Level Mixed Waste

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-09-01

    DOE proposes to transport contact-handled LLMW from the Hanford Site to the Allied Technology Group (ATG) Mixed Waste Facility (MWF) in Richland, Washington, for non-thermal treatment and to return the treated waste to the Hanford Site for eventual land disposal. Over a 3-year period the waste would be staged to the ATG MWF, and treated waste would be returned to the Hanford Site. The ATG MWF would be located on an 18 hectare (ha) (45 acre [at]) ATG Site adjacent to ATG's licensed low-level waste processing facility at 2025 Battelle Boulevard. The ATG MWF is located approximately 0.8 kilometers (km) (0.5 miles [mi]) south of Horn Rapids Road and 1.6 km (1 mi) west of Stevens Drive. The property is located within the Horn Rapids triangle in northern Richland (Figure 2.1). The ATG MWF is to be located on the existing ATG Site, near the DOE Hanford Site, in an industrial area in the City of Richland. The effects of siting, construction, and overall operation of the MWF have been evaluated in a separate State Environmental Policy Act (SEPA) EIS (City of Richland 1998). The proposed action includes transporting the LLMW from the Hanford Site to the ATG Facility, non-thermal treatment of the LLMW at the ATG MWF, and transporting the waste from ATG back to the Hanford Site. Impacts fi-om waste treatment operations would be bounded by the ATG SEPA EIS, which included an evaluation of the impacts associated with operating the non-thermal portion of the MWF at maximum design capacity (8,500 metric tons per year) (City of Richland 1998). Up to 50 employees would be required for non-thermal treatment portion of the MWF. This includes 40 employees that would perform waste treatment operations and 10 support staff. Similar numbers were projected for the thermal treatment portion of the MWF (City of Richland 1998).

  20. Thermal treatment of radioactive wastes by the PLASMARC process

    International Nuclear Information System (INIS)

    Hoffelner, W.; Haefeli, V.; Fuenfschilling, M.R.

    1996-01-01

    The plasma plant for the thermal treatment of radioactive wastes to be supplied to ZWILAG is briefly described and the results of experiments with simulated waste are provided. The experiments led to the conclusion that the plant is well suited for handling low- and intermediate level radioactive wastes. (author) 1 fig., 3 tabs

  1. Radioactive waste management of the radiological accident in Goianaia, Brazil - Cooperation of Waste Treatment Division

    International Nuclear Information System (INIS)

    Guzella, M.F.R.; Miaw, S.T.W.; Reis, L.C.S.; Santos, P.O.; Silva, E.M.P.; Tello, C.C.O.

    1988-01-01

    Radioactive waste were generated in Goiania by an accidental breakage of Cesium 137 radiotherapie source (A=5,0 x 10 13 Bq) in September 1987. The Waste Treatment Division (DITRR.CN) CDTN/NUCLEBRAS has worked in all critical areas to remove the contamination and carried out the tasks at the interim storage. Experience on the waste management and the results from the R and D works conducted by the Division were applied. The R and D works conducted by the Division were applied. The R and D works conducted by the Division were applied. The R and D works comprise package for storage and transport of radioactive material, the use of selected bentonite for Cesium 137 retention, installation of waste treatment facilities and elaboration of several specific procedures. (author) [pt

  2. Operative Fixation Options for Elective and Diabetic Ankle Arthrodesis.

    Science.gov (United States)

    Ramanujam, Crystal L; Stapleton, John J; Zgonis, Thomas

    2017-07-01

    Ankle arthrodesis remains one of the most definitive treatment options for end-stage arthritis, paralysis, posttraumatic and postinfectious conditions, failed total ankle arthroplasty, and severe deformities. The general aims of ankle arthrodesis are to decrease pain and instability, correct the accompanying deformity, and create a stable plantigrade foot. Several surgical approaches have been reported for ankle arthrodesis with internal fixation options. External fixation has also evolved for ankle arthrodesis in certain clinical scenarios. This article provides a comprehensive analysis of midterm to long-term outcomes for ankle arthrodesis using internal and/or external fixation each for elective and diabetic conditions. Copyright © 2017 Elsevier Inc. All rights reserved.

  3. ENGINEERING STUDY FOR THE 200 AREA EFFLUENT TREATMENT FACILITY (ETF) SECONDARY WASTE TREATMENT OF PROJECTED FUTURE WASTE FEEDS

    International Nuclear Information System (INIS)

    LUECK, K.J.

    2004-01-01

    This report documents an engineering study conducted to evaluate alternatives for treating secondary waste in the secondary treatment train (STT) of the Hanford Site 200 Area Effluent Treatment Facility (ETF). The study evaluates ETF STT treatment alternatives and recommends preferred alternatives for meeting the projected future missions of the ETF. The preferred alternative(s) will process projected future ETF influents to produce a solid waste acceptable for final disposal on the Hanford Site. The main text of this report summarizes the ETF past and projected operations, lists the assumptions about projected operations that provide the basis for the engineering evaluation, and summarizes the evaluation process. The evaluation process includes identification of available modifications to the current ETF process, screens those modifications for technical viability, evaluates the technically viable alternatives, and provides conclusions and recommendations based on that evaluation

  4. Modified fixation with pinning and external fixation components for feline femur multiple-lined fracture: A case report

    International Nuclear Information System (INIS)

    Okamoto, Y.; Minami, S.; Matuhashi, A.

    1992-01-01

    A 3-year-old female Japanese domestic cat, weighing 3kg, was referred to us because of right hind leg lameness occuring for 3 days' duration. Radiography of the affected leg revealed severe femoral diaphysial comminuted fracture. The affected leg was treated using wire with an intramedullary Stainman pin being placed completely through the femur. After suturing the wound, both ends of the intramedullary pin exposed both proximally and distally were fixed with external fixation components (two double clamps, two single clamps, two short rods and one long rod) to prevent the pin from rotation. There was a slight gait problem due to the external apparatus and no post-operative infection. The function of the right hind leg gradually recovered. The intramedullary pin and external fixative apparatus were removed on the 52nd day after surgery. This modified fixation appears to offer versatility in the treatment of various fractures in smaller dogs and cats

  5. Electrochemical treatment of liquid wastes

    Energy Technology Data Exchange (ETDEWEB)

    Hobbs, D.T. [Savannah River Technology Center, Aiken, SC (United States)

    1997-10-01

    Under this task, electrochemical treatment processes are being evaluated and developed for the destruction of organic compounds and nitrates/nitrites and the removal of other hazardous species from liquid wastes stored throughout the DOE complex. This technology targets the (1) destruction of nitrates, nitrites and organic compounds; (2) removal of radionuclides; and (3) removal of RCRA metals. The development program consists of five major tasks: (1) evaluation of electrochemical reactors for the destruction and removal of hazardous waste components, (2) development and validation of engineering process models, (3) radioactive laboratory-scale tests, (4) demonstration of the technology in an engineering-scale reactor, and (5) analysis and evaluation of test data. The development program team is comprised of individuals from national laboratories, academic institutions, and private industry. Possible benefits of this technology include: (1) improved radionuclide separation as a result of the removal of organic complexants, (2) reduction in the concentrations of hazardous and radioactive species in the waste (e.g., removal of nitrate, mercury, chromium, cadmium, {sup 99}Tc, and {sup 106}Ru), (3) reduction in the size of the off-gas handling equipment for the vitrification of low-level waste (LLW) by reducing the source of NO{sub x} emissions, (4) recovery of chemicals of value (e.g. sodium hydroxide), and (5) reduction in the volume of waste requiring disposal.

  6. Biological treatment of concentrated hazardous, toxic, andradionuclide mixed wastes without dilution

    Energy Technology Data Exchange (ETDEWEB)

    Stringfellow, William T.; Komada, Tatsuyuki; Chang, Li-Yang

    2004-06-15

    Approximately 10 percent of all radioactive wastes produced in the U. S. are mixed with hazardous or toxic chemicals and therefore can not be placed in secure land disposal facilities. Mixed wastes containing hazardous organic chemicals are often incinerated, but volatile radioactive elements are released directly into the biosphere. Some mixed wastes do not currently have any identified disposal option and are stored locally awaiting new developments. Biological treatment has been proposed as a potentially safer alternative to incineration for the treatment of hazardous organic mixed wastes, since biological treatment would not release volatile radioisotopes and the residual low-level radioactive waste would no longer be restricted from land disposal. Prior studies have shown that toxicity associated with acetonitrile is a significant limiting factor for the application of biotreatment to mixed wastes and excessive dilution was required to avoid inhibition of biological treatment. In this study, we demonstrate that a novel reactor configuration, where the concentrated toxic waste is drip-fed into a complete-mix bioreactor containing a pre-concentrated active microbial population, can be used to treat a surrogate acetonitrile mixed waste stream without excessive dilution. Using a drip-feed bioreactor, we were able to treat a 90,000 mg/L acetonitrile solution to less than 0.1 mg/L final concentration using a dilution factor of only 3.4. It was determined that the acetonitrile degradation reaction was inhibited at a pH above 7.2 and that the reactor could be modeled using conventional kinetic and mass balance approaches. Using a drip-feed reactor configuration addresses a major limiting factor (toxic inhibition) for the biological treatment of toxic, hazardous, or radioactive mixed wastes and suggests that drip-feed bioreactors could be used to treat other concentrated toxic waste streams, such as chemical warfare materiel.

  7. Thermal treatment of high-caloric waste in fluidized bed incineration plants in Austria

    International Nuclear Information System (INIS)

    Ragossnig, A.M.

    2001-05-01

    The importance of thermal treatment of waste and residues in Austria is expected to rise due to the current changes of the legal situation in waste management. Assessing the rank order of different thermal treatment processes for waste management it has been shown that - especially caused by the rising importance of the mechanical treatment step in the mechanical-biological residual waste treatment and the subsequent necessity of the thermal treatment of a high-caloric preprocessed waste stream - the importance of the fluidized bed technology will increase. The main advantages are the high existing capacities as well as the flexibility of this technology in regard of fuel properties and further on the fact of the lacking influence of the ash towards the quality of a product. This is true although the thermal treatment in fluidized bed incinerators requires some processing of the waste. This doctoral thesis also contains a thorough physical and chemical characterization of various waste fuels - especially those which have been used during full scale incineration experiments. This characterization includes a comparison with fossil fuel. The practical part contains the documentation and balancing of full scale incineration experiments. A comparison of a reference experiment with experiments when waste fuel has been thermally utilized showed that a significant increase of emissions to the atmosphere has not been observed. Based on the incineration experiments conclusions in regard of waste fuels as well as different categories of thermal treatment plants are being stated. Finally, a recommendation of the assignation of various waste streams to different categories of thermal treatment plants is being made. (author)

  8. Treatment of Radioactive Organic Wastes by an Electrochemical Oxidation

    International Nuclear Information System (INIS)

    Kim, K.H.; Ryue, Y.G.; Kwak, K.K.; Hong, K.P.; Kim, D.H.

    2007-01-01

    A waste treatment system by using an electrochemical oxidation (MEO, Mediated Electrochemical Oxidation) was installed at KAERI (Korea Atomic Energy Research Institute) for the treatment of radioactive organic wastes, especially EDTA (Ethylene Diamine Tetraacetic Acid) generated during the decontamination activity of nuclear installations. A cerium and silver mediated electrochemical oxidation technique method has been developed as an alternative for an incineration process. An experiment to evaluate the applicability of the above two processes and to establish the conditions to operate the pilot-scale system has been carried out by changing the concentration of the catalyst and EDTA, the operational current density, the operating temperature, and the electrolyte concentration. As for the results, silver mediated oxidation was more effective in destructing the EDTA wastes than the cerium mediated oxidation process. For a constant volume of the EDTA wastes, the treatment time for the cerium-mediated oxidation was 9 hours and its conversion ratio of EDTA to water and CO 2 was 90.2 % at 80 deg. C, 10 A, but the treatment time for the silver-mediated oxidation was 3 hours and its conversion ratio was 89.2 % at 30 deg. C, 10 A. (authors)

  9. Management of paediatric tibial fractures using two types of circular external fixator: Taylor spatial frame and Ilizarov circular fixator.

    Science.gov (United States)

    Tafazal, Suhayl; Madan, Sanjeev S; Ali, Farhan; Padman, Manoj; Swift, Simone; Jones, Stanley; Fernandes, James A

    2014-05-01

    The use of circular fixators for the treatment of tibial fractures is well established in the literature. The aim of this study was to compare the Ilizarov circular fixator (ICF) with the Taylor spatial frame (TSF) in terms of treatment results in consecutive patients with tibial fractures that required operative management. A retrospective analysis of patient records and radiographs was performed to obtain patient data, information on injury sustained, the operative technique used, time duration in frame, healing time and complications of treatment. The minimum follow-up was 24 months. Ten patients were treated with ICF between 2000 and 2005, while 15 patients have been treated with TSF since 2005. Two of the 10 treated with ICF and 5 of the 15 treated with TSF were open fractures. All patients went on to achieve complete union. Mean duration in the frame was 12.7 weeks for ICF and 14.8 weeks for the TSF group. Two patients in the TSF group had delayed union and required additional procedures including adjustment of fixator and bone grafting. There was one malunion in the TSF group that required osteotomy and reapplication of frame. There were seven and nine pin-site infections in the ICF and TSF groups, respectively, all of which responded to antibiotics. There were no refractures in either group. In an appropriate patient, both types of circular fixator are equally effective but have different characteristics, with TSF allowing for postoperative deformity correction. Of concern are the two cases of delayed union in the TSF group, all in patients with high-energy injuries. We feel another larger study is required to provide further clarity in this matter. Level II-comparative study.

  10. Treatment of radioactive liquid organic waste using bacteria community

    International Nuclear Information System (INIS)

    Rafael Vicente de Padua Ferreira; Solange Kazumi Sakata; Maria Helena Bellini; Julio Takehiro Marumo; Fernando Dutra; Patricia Busko Di Vitta; Maria Helena Tirollo Taddei

    2012-01-01

    Waste management plays an important role in radioactive waste volume reduction as well as lowering disposal costs and minimizing the environment-detrimental impact. The employment of biomass in the removal of heavy metals and radioisotopes has a significant potential in liquid waste treatment. The aim of this study is to evaluate the radioactive waste treatment by using three different bacterial communities (BL, BS, and SS) isolated from impacted areas, removing radioisotopes and organic compounds. The best results were obtained in the BS and BL community, isolated from the soil and a lake of a uranium mine, respectively. BS community was able to remove 92% of the uranium and degraded 80% of tributyl phosphate and 70% of the ethyl acetate in 20 days of experiments. BL community removed 81% of the uranium and degraded nearly 60% of the TBP and 70% of the ethyl acetate. SS community collected from the sediment of Sao Sebastiao channel removed 76% of the uranium and 80% of the TBP and 70% of the ethyl acetate. Both americium and cesium were removed by all communities. In addition, the BS community showed to be more resistant to radioactive liquid waste than the other communities. These results indicated that the BS community is the most viable for the treatment of large volumes of radioactive liquid organic waste. (author)

  11. Mixed Waste Integrated Program interim evaluation report on thermal treatment technologies

    International Nuclear Information System (INIS)

    Gillins, R.L.; DeWitt, L.M.; Wollerman, A.L.

    1993-02-01

    The Mixed Waste Integrated Program (MWIP) is one of several US Department of Energy (DOE) integrated programs established to organize and coordinate throughout the DOE complex the development of technologies for treatment of specific waste categories. The goal of the MWIP is to develop and deploy appropriate technologies for -the treatment of DOE mixed low-level and alpha-contaminated wastes in order to bring all affected DOE installations and projects into compliance with environmental laws. Evaluation of treatment technologies by the MWIP will focus on meeting waste form performance requirements for disposal. Thermal treatment technologies were an early emphasis for the MWIP because thermal treatment is indicated (or mandated) for many of the hazardous constituents in DOE mixed waste and because these technologies have been widely investigated for these applications. An advisory group, the Thermal Treatment Working Group (TTWG), was formed during the program's infancy to assist the MWIP in evaluating and prioritizing thermal treatment technologies suitable for development. The results of the overall evaluation scoring indicate that the four highest-rated technologies were rotary kilns, slagging kilns, electric-arc furnaces, and plasma-arc furnaces. The four highest-rated technologies were all judged to be applicable on five of the six waste streams and are the only technologies in the evaluation with this distinction. Conclusions as to the superiority of one technology over others are not valid based on this preliminary study, although some general conclusions can be drawn

  12. Permitting mixed waste treatment, storage and disposal facilities: A mixed bag

    International Nuclear Information System (INIS)

    Ranek, N.L.; Coalgate, J.L.

    1995-01-01

    The Federal Facility Compliance Act of 1992 (FFCAct) requires the U.S. Department of Energy (DOE) to make a comprehensive national inventory of its mixed wastes (i.e., wastes that contain both a hazardous component that meets the Resource Conservation and Recovery Act (RCRA) definition of hazardous waste and a radioactive component consisting of source, special nuclear, or byproduct material regulated under the Atomic Energy Act (AEA)), and of its mixed waste treatment technologies and facilities. It also requires each DOE facility that stores or generates mixed waste to develop a treatment plan that includes, in part, a schedule for constructing units to treat those wastes that can be treated using existing technologies. Inherent in constructing treatment units for mixed wastes is, of course, permitting. This paper identifies Federal regulatory program requirements that are likely to apply to new DOE mixed waste treatment units. The paper concentrates on showing how RCRA permitting requirements interrelate with the permitting or licensing requirements of such other laws as the Atomic Energy Act, the Clean Water Act, and the Clean Air Act. Documentation needed to support permit applications under these laws are compared with RCRA permit application documentation. National Environmental Policy Act (NEPA) documentation requirements are also addressed, and throughout the paper, suggestions are made for managing the permitting process

  13. Induced membrane technique combined with two-stage internal fixation for the treatment of tibial osteomyelitis defects.

    Science.gov (United States)

    Luo, Fei; Wang, Xiaohua; Wang, Shulin; Fu, Jingshu; Xie, Zhao

    2017-07-01

    The purpose of this study was to observe the effects of induced membrane technique combined with two-stage internal fixation in the treatment of tibial osteomyelitis defects. A retrospective analyses for 67 cases of tibialosteomyelitis defects were admitted to our department between September 2012 to February 2015, which were treated with induced membrane technique. At the first stage, implanted with a PMMA cement spacer in the defects after radical debridement and fixed with reconstructive locked plate. Bone grafting and exchanged the plate with intramedullary nail at the second stage. In current study, all patients were followed up for 18-35 months. Sixty-six patients achieved bone union with the average radiographic and clinical healing times of 5.55±2.19 and 7.45±1.69months, respectively. Seven patients required a second debridement before grafting, while four patients experienced a recurrence of infection or a relapse following second stage treatment. Twelve patients experienced either knee or ankle dysfunctions and 2 patients faced delayed wound healing. Donor site complications includes pain and infection were found in 7 and 3 patients, respectively with delayed stress fracture in 1 patient only. Induced membrane technique for the treatment of tibial osteomyelitis defects, seems a reliable method. The use of reconstructive locked plate as a temporary internal fixation at the first stage and exchanged with intramedullary nail at the second stage, potentially achieves good clinical efficacy. Care should be taken to restore the joint function especially in distal tibia. Copyright © 2017 Elsevier Ltd. All rights reserved.

  14. Treatment of liquid wastes from uranium hydrometallurgy

    International Nuclear Information System (INIS)

    Moraga G, J.C.

    1988-01-01

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

  15. Development of treatment technologies of the processing of U.S. Department of Energy mixed waste

    International Nuclear Information System (INIS)

    Backus, P.M.; Berry, J.B.; Coyle, G.J. Jr.; Lurk, P.; Wolf, S.M.

    1994-01-01

    Waste contaminated with chemically hazardous and radioactive species is defined as mixed waste. Significant technology development has been conducted for separate treatment of hazardous and radioactive waste, but technology development addressing mixed-waste treatment has been limited. In response to the need for a comprehensive and consistent approach to mixed-waste technology development, the Office of Technology Development of the US Department of Energy (DOE) has established the Mixed Waste Integrated Program. The program is identifying and evaluating treatment technologies to treat present and estimated future mixed wastes at DOE sites. The status of the technical initiatives in chemical/physical treatment, waste destruction/stabilization technology, off-gas treatment, and final waste form production/assessment is described in this paper

  16. Standard guide for characterization of radioactive and/or hazardous wastes for thermal treatment

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2003-01-01

    1.1 This guide identifies methods to determine the physical and chemical characteristics of radioactive and/or hazardous wastes before a waste is processed at high temperatures, for example, vitrification into a homogeneous glass ,glass-ceramic, or ceramic waste form. This includes waste forms produced by ex-situ vitrification (ESV), in-situ vitrification (ISV), slagging, plasma-arc, hot-isostatic pressing (HIP) and/or cold-pressing and sintering technologies. Note that this guide does not specifically address high temperature waste treatment by incineration but several of the analyses described in this guide may be useful diagnostic methods to determine incinerator off-gas composition and concentrations. The characterization of the waste(s) recommended in this guide can be used to (1) choose and develop the appropriate thermal treatment methodology, (2) determine if waste pretreatment is needed prior to thermal treatment, (3) aid in development of thermal treatment process control, (4) develop surrogate wa...

  17. Treatment of low and intermediate level wastes

    International Nuclear Information System (INIS)

    Hoehlein, G.

    1978-05-01

    The methods described of low and intermediate level waste treatment are based exclusively on operating experience gathered with the KfK facilities for waste management, the Karlsruhe Reprocessing Plant (WAK), the ALKEM fuel element fabrication plant, the MZFR, KNK and FR 2 reactors as well as at the Karlsruhe Nuclear Research Center and at the state collecting depot of Baden-Wuerttemberg. The processing capacities and technical status are similar to that in 1976. With an annual throughput of 10000 m 3 of solid and liquid raw wastes, an aggregate activity of 85000 Ci, 500 kg of U and 2 kg of Pu, final waste in the amount of 500 m 3 was produced which was stored in the ASSE II salt mine. (orig.) [de

  18. Assessment and characterization of radioactive waste for ultimate storage

    International Nuclear Information System (INIS)

    Brennecke, P.; Warnecke, E.

    1986-01-01

    The waste specifications determined from site safety analyses define the requirements to be met by waste forms for ultimate storage. Product quality control is the process step ensuring compliance with the conditions to be met for ultimate storage. For this purpose, radionuclide inventory, fixation method, container type, waste form and quantity, and type of waste are the most significant items on the checking list. (DG) [de

  19. Treatment of solid wastes. Preventing waste production, recovery, waste collection, waste disposal, sanitation. Procedures, technical processes, legal foundations. 2. rev. ed. Behandlung fester Abfaelle. Vermeiden, Verwerten, Sammeln, Beseitigen, Sanieren. Verfahrensweise, technische Realisierung, rechtliche Grundlagen

    Energy Technology Data Exchange (ETDEWEB)

    Sattler, K.; Emberger, J.

    1990-01-01

    The book 'Treatment of Solid Wastes' was compiled by the group 'Environmental Protection/Waste Disposal' and looks at disposal methods and processes. The initial chapters deal with technical methods of environmental protection, describe laws and legal regulations pertaining to waste disposal, explain the quantities and composition of the waste matter and give an overview of the treatments which are available. Methods and technical process of waste collection, transport, sorting, recapturing of valuable matter, biochemical and thermal conversion and depositing. Treatment of poisonous wastes and old sites are dealt with in the final chapters. (orig./EF).

  20. Process of liquid radioactive waste treatment in nuclear power plant and development trend

    International Nuclear Information System (INIS)

    Liu Jiean; Wang Xin; Liu Dan; Zhu Laiye; Chen Bin

    2014-01-01

    The popular liquid radioactive waste treatment methods in nuclear power plants (NPP) are Chemical precipitation, evaporation, ion exchange, membrane treatment, chemical coagulation and activated carbon absorption and so on. 'Filter + activated carbon absorption (Chemical coagulation) + ion exchange' has a good prospect for development, as its simple process, high decontamination factor, low energy consumption and smaller secondary wastes. Also the process is used in Sanmen and Haiyang Projects. The severe incident in NPP set an even higher demand on liquid radioactive waste treatment. The new type treatment materials, optimization of the existed treatment, combination of treatment and the mobile treatment facility is the development trend in liquid radioactive waste treatment in NPP. (authors)

  1. A Database for Reviewing and Selecting Radioactive Waste Treatment Technologies and Vendors

    International Nuclear Information System (INIS)

    P. C. Marushia; W. E. Schwinkendorf

    1999-01-01

    Several attempts have been made in past years to collate and present waste management technologies and solutions to waste generators. These efforts have been manifested as reports, buyers' guides, and databases. While this information is helpful at the time it is assembled, the principal weakness is maintaining the timeliness and accuracy of the information over time. In many cases, updates have to be published or developed as soon as the product is disseminated. The recently developed National Low-Level Waste Management Program's Technologies Database is a vendor-updated Internet based database designed to overcome this problem. The National Low-Level Waste Management Program's Technologies Database contains information about waste types, treatment technologies, and vendor information. Information is presented about waste types, typical treatments, and the vendors who provide those treatment methods. The vendors who provide services update their own contact information, their treatment processes, and the types of wastes for which their treatment process is applicable. This information is queriable by a generator of low-level or mixed low-level radioactive waste who is seeking information on waste treatment methods and the vendors who provide them. Timeliness of the information in the database is assured using time clocks and automated messaging to remind featured vendors to keep their information current. Failure to keep the entries current results in a vendor being warned and then ultimately dropped from the database. This assures that the user is dealing with the most current information available and the vendors who are active in reaching and serving their market

  2. Tank waste remediation system optimized processing strategy with an altered treatment scheme

    International Nuclear Information System (INIS)

    Slaathaug, E.J.

    1996-03-01

    This report provides an alternative strategy evolved from the current Hanford Site Tank Waste Remediation System (TWRS) programmatic baseline for accomplishing the treatment and disposal of the Hanford Site tank wastes. This optimized processing strategy with an altered treatment scheme performs the major elements of the TWRS Program, but modifies the deployment of selected treatment technologies to reduce the program cost. The present program for development of waste retrieval, pretreatment, and vitrification technologies continues, but the optimized processing strategy reuses a single facility to accomplish the separations/low-activity waste (LAW) vitrification and the high-level waste (HLW) vitrification processes sequentially, thereby eliminating the need for a separate HLW vitrification facility

  3. Mixed Waste Focus Area mercury contamination product line: An integrated approach to mercury waste treatment and disposal

    International Nuclear Information System (INIS)

    Hulet, G.A.; Conley, T.B.; Morris, M.I.

    1998-01-01

    The US Department of Energy (DOE) Mixed Waste Focus Area (MWFA) is tasked with ensuring that solutions are available for the mixed waste treatment problems of the DOE complex. During the MWFA's initial technical baseline development process, three of the top four technology deficiencies identified were related to the need for amalgamation, stabilization, and separation/removal technologies for the treatment of mercury and mercury-contaminated mixed waste. The focus area grouped mercury-waste-treatment activities into the mercury contamination product line under which development, demonstration, and deployment efforts are coordinated to provide tested technologies to meet the site needs. The Mercury Working Group (HgWG), a selected group of representatives from DOE sites with significant mercury waste inventories, is assisting the MWFA in soliciting, identifying, initiating, and managing efforts to address these areas. Based on the scope and magnitude of the mercury mixed waste problem, as defined by HgWG, solicitations and contract awards have been made to the private sector to demonstrate amalgamation and stabilization processes using actual mixed wastes. Development efforts are currently being funded under the product line that will address DOE's needs for separation/removal processes. This paper discusses the technology selection process, development activities, and the accomplishments of the MWFA to date through these various activities

  4. Basic design of alpha aqueous waste treatment process in NUCEF

    Energy Technology Data Exchange (ETDEWEB)

    Mineo, Hideaki; Matsumura, Tatsuro; Nishizawa, Ichio; Mitsui, Takeshi; Ueki, Hiroyuki; Wada, Atsushi; Sakai, Ichita; Takeshita, Isao [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Nishimura, Kenji

    1996-11-01

    This paper described the basic design of Alpha Aqueous Waste Treatment Process in NUCEF. Since various experiments using the TRU (transuranium) elements are carried out in NUCEF, wastes containing TRU elements arise. The liquid wastes in NUCEF are categorized into three types. Decontamination and volume reduction of the liquid waste mainly of recovery water from acid recovery process which has lowest radioactive concentration is the most important task, because the arising rate of the waste is large. The major function of the Alpha Aqueous Waste Treatment Process is to decontaminate the radioactive concentration below the level which is allowed to discharge into sea. Prior the process design of this facility, the followings are evaluated:property and arising rate of the liquid waste, room space to install and licensing condition. Considering varieties of liquid wastes and their large volume, the very high decontamination factor was proposed by a process of multiple evaporation supported with filtration and adsorption in the head end part and reverse osmosis in the distillate part. (author)

  5. Treatment of atlantoaxial rotatory fixation with botulinum toxin muscle block and manipulation.

    Science.gov (United States)

    Lin, Chia-Hung; Chen, Chun-Jung; Chen, Chuan-Mu; Liao, Su-Lan; Raung, Shue-Ling; Tsai, Sen-Wei

    2010-04-01

    Slippage after reduction of atlantoaxial rotatory fixation (AARF) is usually treated with repeated cervical traction and brace immobilization. To date, no data have been published on the management of muscle spasm during treatment. Here, we describe the case of a 7-year-old girl with AARF for 1 month who visited our hospital for treatment. During physical examination, spasm of the sternocleidomastoid muscle was noted. The patient was treated with manipulative reduction, and slippage after reduction was managed with botulinum spasticity block of the sternocleidomastoid and splenius capitis muscles, and repeated manipulation. Cervical orthosis immobilization with a rehabilitation program of isometric contract-relax exercise for the neck was conducted for 3 months. The subject had full recovery from AARF at 1-year follow-up. This report demonstrates that, in selected cases of slippage after reduction from AARF, conservative management with manipulation under anesthesia is a good method, and the muscle components may play a crucial role in AARF. Copyright 2010 Elsevier. Published by Elsevier B.V. All rights reserved.

  6. Thermal co-treatment of combustible hazardous waste and waste incineration fly ash in a rotary kiln.

    Science.gov (United States)

    Huber, Florian; Blasenbauer, Dominik; Mallow, Ole; Lederer, Jakob; Winter, Franz; Fellner, Johann

    2016-12-01

    As current disposal practices for municipal solid waste incineration (MSWI) fly ash are either associated with significant costs or negative environmental impacts, an alternative treatment was investigated in a field scale experiment. Thereto, two rotary kilns were fed with hazardous waste, and moistened MSWI fly ash (water content of 23%) was added to the fuel of one kiln with a ratio of 169kg/Mg hazardous waste for 54h and 300kg/Mg hazardous waste for 48h while the other kiln was used as a reference. It was shown that the vast majority (>90%) of the inserted MSWI fly ash was transferred to the bottom ash of the rotary kiln. This bottom ash complied with the legal limits for non-hazardous waste landfills, thereby demonstrating the potential of the investigated method to transfer hazardous waste (MSWI fly ash) into non-hazardous waste (bottom ash). The results of a simple mixing test (MSWI fly ash and rotary kiln bottom ash have been mixed accordingly without thermal treatment) revealed that the observed transformation of hazardous MSWI fly ash into non-hazardous bottom ash during thermal co-treatment cannot be referred to dilution, as the mixture did not comply with legal limits for non-hazardous waste landfills. For the newly generated fly ash of the kiln, an increase in the concentration of Cd, K and Pb by 54%, 57% and 22%, respectively, was observed. In general, the operation of the rotary kiln was not impaired by the MSWI fly ash addition. Copyright © 2016 Elsevier Ltd. All rights reserved.

  7. Proposal of an environmental performance index to assess solid waste treatment technologies

    International Nuclear Information System (INIS)

    Goulart Coelho, Hosmanny Mauro; Lange, Liséte Celina; Coelho, Lineker Max Goulart

    2012-01-01

    Highlights: ► Proposal of a new concept in waste management: Cleaner Treatment. ► Development of an index to assess quantitatively waste treatment technologies. ► Delphi Method was carried out so as to define environmental indicators. ► Environmental performance evaluation of waste-to-energy plants. - Abstract: Although the concern with sustainable development and environment protection has considerably grown in the last years it is noted that the majority of decision making models and tools are still either excessively tied to economic aspects or geared to the production process. Moreover, existing models focus on the priority steps of solid waste management, beyond waste energy recovery and disposal. So, in order to help the lack of models and tools aiming at the waste treatment and final disposal, a new concept is proposed: the Cleaner Treatment, which is based on the Cleaner Production principles. This paper focuses on the development and validation of the Cleaner Treatment Index (CTI), to assess environmental performance of waste treatment technologies based on the Cleaner Treatment concept. The index is formed by aggregation (summation or product) of several indicators that consists in operational parameters. The weights of the indicator were established by Delphi Method and Brazilian Environmental Laws. In addition, sensitivity analyses were carried out comparing both aggregation methods. Finally, index validation was carried out by applying the CTI to 10 waste-to-energy plants data. From sensitivity analysis and validation results it is possible to infer that summation model is the most suitable aggregation method. For summation method, CTI results were superior to 0.5 (in a scale from 0 to 1) for most facilities evaluated. So, this study demonstrates that CTI is a simple and robust tool to assess and compare the environmental performance of different treatment plants being an excellent quantitative tool to support Cleaner Treatment implementation.

  8. The Treatment of Mixed Waste with GeoMelt In-Container Vitrification

    International Nuclear Information System (INIS)

    Finucane, K.G.; Campbell, B.E.

    2006-01-01

    AMEC's GeoMelt R In-Container Vitrification (ICV) TM has been used to treat diverse types of mixed low-level radioactive waste. ICV is effective in the treatment of mixed wastes containing polychlorinated biphenyls (PCBs) and other semi-volatile organic compounds, volatile organic compounds (VOCs) and heavy metals. The GeoMelt vitrification process destroys organic compounds and immobilizes metals and radionuclides in an extremely durable glass waste form. The process is flexible allowing for treatment of aqueous, oily, and solid mixed waste, including contaminated soil. In 2004, ICV was used to treat mixed radioactive waste sludge containing PCBs generated from a commercial cleanup project regulated by the Toxic Substances Control Act (TSCA), and to treat contaminated soil from Rocky Flats Environmental Technology Site. The Rocky Flats soil contained cadmium, PCBs, and depleted uranium. In 2005, AMEC completed a treatability demonstration of the ICV technology on Mock High Explosive from Sandia National Laboratories. This paper summarizes results from these mixed waste treatment projects. (authors)

  9. Posterior Decompression, Lumber Interbody Fusion and Internal Fixation in the Treatment of Upper Lumbar Intervertebral Disc Herniation

    Directory of Open Access Journals (Sweden)

    DONG Zhan

    2014-12-01

    Full Text Available Objective: To assess the clinical outcomes of posterior decompression, interbody fusion and internal fixationfor the treatment of the upper lumbar intervertebral disc herniation. Methods: Twelve patients with the upper lumbar intervertebral disc herniation were treated by posterior decompression, interbosy fusion and internal fixation. The time of the operation, the amount of bleeding and the clinical efficacy were evaluated. Results: The time of operation was (143±36 min and the amount of bleeding during operation was (331.5±47.9 mL. There was no spinal cord and injuries, nerve injury, epidural damage and leakage of cerebrospinal fluid. All patients were followed up for 10~19 months with the average being 12.6 months. The functional scoring of Japanese Orthopedic Association (JOA before the operation was (11.4±3.3 scores and final score after follow-up was (22.9±3.1 scores and there were statistical difference (P<0.01. Lumber interbody fusion of all patients completed successfully and the good rate after the operation was 91.7%. Conclusion: Posterior decompression, interbody fusion and internal fixation for the treatment of the upper lumbar intervertebral disc herniation was characterized by full exposure, safety and significant efficacy.

  10. Radioactive Demonstrations Of Fluidized Bed Steam Reforming As A Supplementary Treatment For Hanford's Low Activity Waste And Secondary Wastes

    International Nuclear Information System (INIS)

    Jantzen, C.; Crawford, C.; Cozzi, A.; Bannochie, C.; Burket, P.; Daniel, G.

    2011-01-01

    The U.S. Department of Energy's Office of River Protection (ORP) is responsible for the retrieval, treatment, immobilization, and disposal of Hanford's tank waste. Currently there are approximately 56 million gallons of highly radioactive mixed wastes awaiting treatment. A key aspect of the River Protection Project (RPP) cleanup mission is to construct and operate the Waste Treatment and Immobilization Plant (WTP). The WTP will separate the tank waste into high-level and low-activity waste (LAW) fractions, both of which will subsequently be vitrified. The projected throughput capacity of the WTP LAW Vitrification Facility is insufficient to complete the RPP mission in the time frame required by the Hanford Federal Facility Agreement and Consent Order, also known as the Tri-Party Agreement (TPA), i.e. December 31, 2047. Therefore, Supplemental Treatment is required both to meet the TPA treatment requirements as well as to more cost effectively complete the tank waste treatment mission. The Supplemental Treatment chosen will immobilize that portion of the retrieved LAW that is not sent to the WTP's LAW Vitrification facility into a solidified waste form. The solidified waste will then be disposed on the Hanford site in the Integrated Disposal Facility (IDF). In addition, the WTP LAW vitrification facility off-gas condensate known as WTP Secondary Waste (WTP-SW) will be generated and enriched in volatile components such as Cs-137, I-129, Tc-99, Cl, F, and SO4 that volatilize at the vitrification temperature of 1150 C in the absence of a continuous cold cap. The current waste disposal path for the WTP-SW is to recycle it to the supplemental LAW treatment to avoid a large steady state accumulation in the pretreatment-vitrification loop. Fluidized Bed Steam Reforming (FBSR) offers a moderate temperature (700-750 C) continuous method by which LAW and/or WTP-SW wastes can be processed irrespective of whether they contain organics, nitrates, sulfates/sulfides, chlorides

  11. Support of the radioactive waste treatment nuclear fuel fabrication facility

    International Nuclear Information System (INIS)

    Park, H.H.; Han, K.W.; Lee, B.J.; Shim, G.S.; Chung, M.S.

    1982-01-01

    Technical service of radioactive waste treatment in Daeduck Engineering Center includes; 1) Treatment of radioactive wastes from the nuclear fuel fabrication facility and from laboratories. 2) Establishing a process for intermediate treatment necessary till the time when RWTF is in completion. 3) Technical evaluation of unit processes and equipments concerning RWTF. About 35 drums (8 m 3 ) of solid wastes were treated and stored while more than 130 m 3 of liquid wastes were disposed or stored. A process with evaporators of 10 1/hr in capacity, a four-stage solvent washer, storage tanks and disposal system was designed and some of the equipments were manufactured. Concerning RWTF, its process was reviewed technically and emphasis were made on stability of the bituminization process against explosion, function of PAAC pump, decontamination, and finally on problems to be solved in the comming years. (Author)

  12. Outcome of complex tibial plateau fractures treated with external fixator

    Directory of Open Access Journals (Sweden)

    Sushil H Mankar

    2012-01-01

    Conclusion: We believe that minimally invasive treatment by percutaneous techniques and external fixation is a fairly reasonable treatment alternative, if near anatomical reduction of joint surface can be confirmed on fluoroscopy.

  13. Comparison of Outcomes of Operatively Treated Bicondylar Tibial Plateau Fractures by External Fixation and Internal Fixation

    Directory of Open Access Journals (Sweden)

    CC Chan

    2012-03-01

    Full Text Available The outcome of bicondylar tibial plateau fractures treated with either external fixation (35 patients or internal fixation (24 patients was reviewed. Outcome measures included the Rasmussen score, clinical complications, development of osteoarthritis and the requirement for total knee replacement (TKR. Twenty-two (92% anatomical reductions were achieved in the internal fixation group compared to 27 (77% in the external fixation group. Infective complications were more common in the external fixation group (9 patients, 26% due to pin tract infection. There were no deep infections in the internal fixation group. The mean Rasmussen score was not significantly different (mean score 32 in external fixation and 29 in internal fixation between the two groups and the incidence of osteoarthritis was the same in both groups. Four patients in the external fixation group underwent a TKR compared to 5 patients in the internal fixation group. Bicondylar tibial plateau fractures have similar outcomes following external or internal fixation.

  14. Electrical processes for liquid waste treatment

    International Nuclear Information System (INIS)

    Turner, A.D.; Bridger, N.J.; Junkison, A.R.; Pottinger, J.S.

    1987-08-01

    This report describes the development of electrical techniques for the treatment of liquid waste streams. Part I is concerned with solid/liquid separation and the demonstration of the electrokinetic thickening of flocs at inorganic membranes suitable for intermediate-level wastes and electrochemical cleaning of stainless steel microfilters and graphite ultrafilters. Part II describes work on the development of electrochemical ion exchange, particularly the use of inorganic absorption media and polarity reversal to enhance system selectivity. Work on the adsorption and desorption of plutonium in acid nitrate solution at various electrode materials is also included. (author)

  15. Large fluctuations and fixation in evolutionary games

    International Nuclear Information System (INIS)

    Assaf, Michael; Mobilia, Mauro

    2010-01-01

    We study large fluctuations in evolutionary games belonging to the coordination and anti-coordination classes. The dynamics of these games, modeling cooperation dilemmas, is characterized by a coexistence fixed point separating two absorbing states. We are particularly interested in the problem of fixation that refers to the possibility that a few mutants take over the entire population. Here, the fixation phenomenon is induced by large fluctuations and is investigated by a semiclassical WKB (Wentzel–Kramers–Brillouin) theory generalized to treat stochastic systems possessing multiple absorbing states. Importantly, this method allows us to analyze the combined influence of selection and random fluctuations on the evolutionary dynamics beyond the weak selection limit often considered in previous works. We accurately compute, including pre-exponential factors, the probability distribution function in the long-lived coexistence state and the mean fixation time necessary for a few mutants to take over the entire population in anti-coordination games, and also the fixation probability in the coordination class. Our analytical results compare excellently with extensive numerical simulations. Furthermore, we demonstrate that our treatment is superior to the Fokker–Planck approximation when the selection intensity is finite

  16. Locking plate fixation for proximal humerus fractures.

    LENUS (Irish Health Repository)

    Burke, Neil G

    2012-02-01

    Locking plates are increasingly used to surgically treat proximal humerus fractures. Knowledge of the bone quality of the proximal humerus is important. Studies have shown the medial and dorsal aspects of the proximal humeral head to have the highest bone strength, and this should be exploited by fixation techniques, particularly in elderly patients with osteoporosis. The goals of surgery for proximal humeral fractures should involve minimal soft tissue dissection and achieve anatomic reduction of the head complex with sufficient stability to allow for early shoulder mobilization. This article reviews various treatment options, in particular locking plate fixation. Locking plate fixation is associated with a high complication rate, such as avascular necrosis (7.9%), screw cutout (11.6%), and revision surgery (13.7%). These complications are frequently due to the varus deformation of the humeral head. Strategic screw placement in the humeral head would minimize the possibility of loss of fracture reduction and potential hardware complications. Locking plate fixation is a good surgical option for the management of proximal humerus fractures. Complications can be avoided by using better bone stock and by careful screw placement in the humeral head.

  17. Electrochemical treatment of liquid wastes

    International Nuclear Information System (INIS)

    Hobbs, D.

    1996-01-01

    Electrochemical treatment processes are being evaluated and developed for the destruction of organic compounds and nitrates/nitrites and the removal of other hazardous species from liquid wastes stored throughout the DOE complex. This activity consists of five major tasks: (1) evaluation of different electrochemical reactors for the destruction and removal of hazardous waste components, (2) development and validation of engineering process models, (3) radioactive laboratory-scale tests, (4) demonstration of the technology in an engineering-scale size reactor, and (5) analysis and evaluation of testing data. The development program team is comprised of individuals from federal, academic, and private industry. Work is being carried out in DOE, academic, and private industrial laboratories

  18. Smaller Fixation Target Size Is Associated with More Stable Fixation and Less Variance in Threshold Sensitivity.

    Directory of Open Access Journals (Sweden)

    Kazunori Hirasawa

    Full Text Available The aims of this randomized observational case control study were to quantify fixation behavior during standard automated perimetry (SAP with different fixation targets and to evaluate the relationship between fixation behavior and threshold variability at each test point in healthy young participants experienced with perimetry. SAP was performed on the right eyes of 29 participants using the Octopus 900 perimeter, program 32, dynamic strategy. The fixation targets of Point, Cross, and Ring were used for SAP. Fixation behavior was recorded using a wearable eye-tracking glass. All participants underwent SAP twice with each fixation target in a random fashion. Fixation behavior was quantified by calculating the bivariate contour ellipse area (BCEA and the frequency of deviation from the fixation target. The BCEAs (deg2 of Point, Cross, and Ring targets were 1.11, 1.46, and 2.02, respectively. In all cases, BCEA increased significantly with increasing fixation target size (p < 0.05. The logarithmic value of BCEA demonstrated the same tendency (p < 0.05. A positive correlation was identified between fixation behavior and threshold variability for the Point and Cross targets (ρ = 0.413-0.534, p < 0.05. Fixation behavior increased with increasing fixation target size. Moreover, a larger fixation behavior tended to be associated with a higher threshold variability. A small fixation target is recommended during the visual field test.

  19. Treatment of low alpha activity liquid wastes

    International Nuclear Information System (INIS)

    Nannicini, R.; Fenoglio, F.; Pozzi, L.

    1984-01-01

    The nuclear industry considers so big safety problems that the purifying treatment of liquid wastes must always provide for a complete recycle of the liquid strems from the production processes as regard this problem. ''Enea-Comb-Ifec'' people from saluggia, already previously engages with verifying and setting-up ''Sol-Gel'' process for the recover of uranium-plutonium solutions coming from irradiated fuel reprocessing, started an experimental work, with the assistance of ''Cnr-Irsa'' from Rome, on the applicability of the biological treatment to the purification of liquid wastes coming from the production process itself. The present technical report gives, besides a short description of the ''Sol-Gel'' process, the first results, only relating to the biological stage of the whole proposed purifyng treatment, included the final results of the experimental work, object of a contract between ''Enea-Ifec'' and ''Snam progetti'' from Fano

  20. [Clinical efficacy of unilateral percutaneous transfacet screws combined with contralateral pedicle screw versus bilateral pedicle screws fixation in the treatment of the degenerative lumbar disease].

    Science.gov (United States)

    Hao, Rong-Xue; Zhou, Hui; Pan, Hao; Yue, Jun; Chen, Hui-Guo; Yang, He-Jie; Jia, Gao-Yong; Wang, Dong; Lin, Yan; Xu, Hua-Zi

    2017-09-25

    To investigate the surgical outcome of unilateral pedicle screw(UPS) after TLIF technique combined with contralateral percutaneous transfacet screw(PTS) fixation vs bilateral pedicle screws(BPS) fixation in treatment of degenerative lumbar disease. From January 2009 to June 2012, 46 patients with degenerative lumbar diseases, including 30 males and 16 females with an average age of 51.5 years old, who were divided into two groups according to different fixation methods. Twenty-two cases underwent UPS after TLIF technique combined with contralateral PTS fixation (group A), while the others underwent BPS fixation(group B). The relative data were analyzed, such as blood loss volume, operative time, fusion rate, ODI score, JOA score and so on. All the patients were followed up for 1 to 3 years with an average of 22 months. Except one case of each group was uncertainty fusion, the rest have obtained bony fusion, and the fusion rates in group A and B were 95.5% and 95.8%, respectively. No displacement and breakage of screw were found during follow-up. Operative time and blood loss volume in group A were better than of group B( P 0.05). Two approaches had similar clinical outcomes for degenerative lumbar disease with no severe instability. Compared with BPS fixation, the UPS after TLIF technique and contralateral PTS fixation has the advantages of less trauma, shorter operative time and less blood loss, and it is a safe and feasible surgical technique.

  1. Immobilization of high level nuclear wastes in sintered glasses. Devitrification evaluation produced with different thermal treatments

    International Nuclear Information System (INIS)

    Messi de Bernasconi, N.B.; Russo, D.O.; Bevilacqua, M.E.; Sterba, M.E.; Heredia, A.D.; Audero, M.A.

    1990-01-01

    This work describes immobilization of high level nuclear wastes in sintered glass, as alternative way to melting glass. Different chemical compositions of borosilicate glass with simulate waste were utilized and satisfactory results were obtained at laboratory scale. As another contribution to the materials studies by X ray powder diffraction analysis, the devitrification produced with different thermal treatments, was evaluated. The effect of the thermal history on the behaviour of fission products containing glasses has been studied by several working groups in the field of high level waste fixation. When the glass is cooled through the temperature range from 800 deg C down to less than 400 deg C (these temperatures are approximates) nucleation and crystal growth can take place. The rate of crystallization will be maximum near the transformation point but through this rate may be low at lower temperatures, devitrification can still occur over long periods of time, depending on the glass composition. It was verified that there can be an appreciable increase in leaching in some waste glass compositions owing to the presence of crystalline phases. On the other hand, other compositions show very little change in leachability and the devitrified product is often preferable as there is less tendency to cracking, particularly in massive blocks of glass. A borosilicate glass, named SG7, which was developed specially in the KfK for the hot pressing of HLW with glass frit was studied. It presents a much enhanced chemical durability than borosolicate glass developed for the melting process. The crystallization behaviour of SG7 glass products was investigated in our own experiments by annealing sintered samples up to 3000 h at temperatures between 675 and 825 deg C. The samples had contained simulated waste with noble metals, since these might act as foreign nuclei for crystallization. Results on the extent of devitrification and time- temperature- transformation curves are

  2. Radioactive Demonstration Of Final Mineralized Waste Forms For Hanford Waste Treatment Plant Secondary Waste By Fluidized Bed Steam Reforming Using The Bench Scale Reformer Platform

    International Nuclear Information System (INIS)

    Crawford, C.; Burket, P.; Cozzi, A.; Daniel, W.; Jantzen, C.; Missimer, D.

    2012-01-01

    The U.S. Department of Energy's Office of River Protection (ORP) is responsible for the retrieval, treatment, immobilization, and disposal of Hanford's tank waste. Currently there are approximately 56 million gallons of highly radioactive mixed wastes awaiting treatment. A key aspect of the River Protection Project (RPP) cleanup mission is to construct and operate the Waste Treatment and Immobilization Plant (WTP). The WTP will separate the tank waste into high-level and low-activity waste (LAW) fractions, both of which will subsequently be vitrified. The projected throughput capacity of the WTP LAW Vitrification Facility is insufficient to complete the RPP mission in the time frame required by the Hanford Federal Facility Agreement and Consent Order, also known as the Tri-Party Agreement (TPA), i.e. December 31, 2047. Therefore, Supplemental Treatment is required both to meet the TPA treatment requirements as well as to more cost effectively complete the tank waste treatment mission. In addition, the WTP LAW vitrification facility off-gas condensate known as WTP Secondary Waste (WTP-SW) will be generated and enriched in volatile components such as 137 Cs, 129 I, 99 Tc, Cl, F, and SO 4 that volatilize at the vitrification temperature of 1150 C in the absence of a continuous cold cap (that could minimize volatilization). The current waste disposal path for the WTP-SW is to process it through the Effluent Treatment Facility (ETF). Fluidized Bed Steam Reforming (FBSR) is being considered for immobilization of the ETF concentrate that would be generated by processing the WTP-SW. The focus of this current report is the WTP-SW. FBSR offers a moderate temperature (700-750 C) continuous method by which WTP-SW wastes can be processed irrespective of whether they contain organics, nitrates, sulfates/sulfides, chlorides, fluorides, volatile radionuclides or other aqueous components. The FBSR technology can process these wastes into a crystalline ceramic (mineral) waste form

  3. Treatment Study Plan for Nitrate Salt Waste Remediation Revision 1.0

    Energy Technology Data Exchange (ETDEWEB)

    Juarez, Catherine L. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Funk, David John [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Vigil-Holterman, Luciana R. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Naranjo, Felicia Danielle [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2016-03-07

    The two stabilization treatment methods that are to be examined for their effectiveness in the treatment of both the unremediated and remediated nitrate salt wastes include (1) the addition of zeolite and (2) cementation. Zeolite addition is proposed based on the results of several studies and analyses that specifically examined the effectiveness of this process for deactivating nitrate salts. Cementation is also being assessed because of its prevalence as an immobilization method used for similar wastes at numerous facilities around the DOE complex, including at Los Alamos. The results of this Treatment Study Plan will be used to provide the basis for a Resource Conservation and Recovery Act (RCRA) permit modification request of the LANL Hazardous Waste Facility Permit for approval by the New Mexico Environment Department-Hazardous Waste Bureau (NMED-HWB) of the proposed treatment process and the associated facilities.

  4. Treatment and final conditioning of solid radioactive wastes

    International Nuclear Information System (INIS)

    Cerre, J.

    1960-01-01

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

  5. Two-stage open reduction and internal fixation versus limited internal fixation combined with external fixation: a meta-analysis of postoperative complications in patients with severe Pilon fractures.

    Science.gov (United States)

    Cui, Xueliang; Chen, Hui; Rui, Yunfeng; Niu, Yang; Li, He

    2018-01-01

    Objectives Two-stage open reduction and internal fixation (ORIF) and limited internal fixation combined with external fixation (LIFEF) are two widely used methods to treat Pilon injury. However, which method is superior to the other remains controversial. This meta-analysis was performed to quantitatively compare two-stage ORIF and LIFEF and clarify which method is better with respect to postoperative complications in the treatment of tibial Pilon fractures. Methods We conducted a meta-analysis to quantitatively compare the postoperative complications between two-stage ORIF and LIFEF. Eight studies involving 360 fractures in 359 patients were included in the meta-analysis. Results The two-stage ORIF group had a significantly lower risk of superficial infection, nonunion, and bone healing problems than the LIFEF group. However, no significant differences in deep infection, delayed union, malunion, arthritis symptoms, or chronic osteomyelitis were found between the two groups. Conclusion Two-stage ORIF was associated with a lower risk of postoperative complications with respect to superficial infection, nonunion, and bone healing problems than LIFEF for tibial Pilon fractures. Level of evidence 2.

  6. Energy requirements for waste water treatment.

    Science.gov (United States)

    Svardal, K; Kroiss, H

    2011-01-01

    The actual mathematical models describing global climate closely link the detected increase in global temperature to anthropogenic activity. The only energy source we can rely on in a long perspective is solar irradiation which is in the order of 10,000 kW/inhabitant. The actual primary power consumption (mainly based on fossil resources) in the developed countries is in the range of 5 to 10 kW/inhabitant. The total power contained in our nutrition is in the range of 0.11 kW/inhabitant. The organic pollution of domestic waste water corresponds to approximately 0.018 kW/inhabitant. The nutrients contained in the waste water can also be converted into energy equivalents replacing market fertiliser production. This energy equivalent is in the range of 0.009 kW/inhabitant. Hence waste water will never be a relevant source of energy as long as our primary energy consumption is in the range of several kW/inhabitant. The annual mean primary power demand of conventional municipal waste water treatment with nutrient removal is in the range of 0.003-0.015 kW/inhabitant. In principle it is already possible to reduce this value for external energy supply to zero. Such plants should be connected to an electrical grid in order to keep investment costs low. Peak energy demand will be supported from the grid and surplus electric energy from the plant can be is fed to the grid. Zero 'carbon footprint' will not be affected by this solution. Energy minimisation must never negatively affect treatment efficiency because water quality conservation is more important for sustainable development than the possible reduction in energy demand. This argument is strongly supported by economical considerations as the fixed costs for waste water infrastructure are dominant.

  7. Plasma arc melting treatment of low level radioactive waste with centrifugal hearth

    International Nuclear Information System (INIS)

    Tsuji, Yukito

    1997-01-01

    Plasma Arc Melting technology may possible be able to treat various kinds of waste streams through volume reduction and stabilization into a disposal waste form. The ability of other melting technologies to convert inorganic material in a single step, however, varies according to the characteristics of the materials. Plasma technology also can treat organic waste by selecting the oxidation atmosphere. The Japan Atomic Power Company (JAPC) has decided to construct a low level radioactive waste treatment facility using the Plasma Arc Centrifugal Treatment (PACT) process with an 8 ft rotating hearth and 1.2 MW transferred torch developed by Retech (Ukiah, CA. USA) in the Tsuruga power station. In Japan, the plasma technology has been developed for incineration ash treatment, but the JAPC plant will be the first treatment system using plasma technology for solid waste with various characteristics and shapes. (author)

  8. A Multi-Criteria Decision Analysis of Waste Treatment Options for Food and Biodegradable Waste Management in Japan

    Directory of Open Access Journals (Sweden)

    Micky A. Babalola

    2015-10-01

    Full Text Available Dealing with large-scale Food and Biodegradable Waste (FBW often results in many logistical problems and environmental impacts to be considered. These can become great hindrances when the integration of solid waste management is concerned. Extra care is needed to plan such waste disposal or treatment services and facilities, especially with respect to the ecological impact. Decision-making with regards to the sustainable use of these facilities also involves tradeoffs between a number of conflicting objectives, since increasing one benefit may decrease the others. In this study a Multi-Criteria Decision Analysis (MCDA is presented to evaluate different waste management options and their applicability in Japan. The analytical process aims at selecting the most suitable waste treatment option, using pairwise comparisons conducted within a decision hierarchy that was developed through the Analytical Hierarchy Process (AHP. The results of this study show that anaerobic digestion should be chosen as the best FBW treatment option with regards to resource recovery. The study also presents some conditions and recommendations that can enhance the suitability of other options like incineration and composting.

  9. Decontamination factor Improvement and Waste Reduction of Full-scaled Evaporation System for Liquid Radioactive Waste Treatment

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Ki Tae; Ju, Young Jong; Seol, Jeung Gun; Cho, Nam Chan [KNF, Daejeon (Korea, Republic of); Ha, Dong Hwan; Kim, Yun Kwan [Jeontech Co., Suwon (Korea, Republic of)

    2016-05-15

    Liquid radioactive waste is produced from nuclear power plants, nuclear research centers, radiopharmaceuticals and nuclear fuel fabrication plants, etc. Ion-exchange, chemical precipitation, evaporation, filtration, liquid/solid extraction and centrifugal are applied to treat the liquid waste. Chemical precipitation requires low capital and operation cost. However, it produces large amount of secondary waste and has low DF (decontamination factor). Evaporation process removes variety of radionuclides in high DF. But, it also has problems in scaling and foaming [3, 4]. In this study, it is investigated that the effect of switching lime precipitation and centrifugal processes to evaporation system for improvement of removal efficiency and decrease of waste in full-scaled radioactive wastewater treatment plant. By swapping full-scaled wastewater treatment system from the centrifugal and the lime precipitation to the evaporator and the crystallizer in the nuclear fuel fabrication plant, it was possible to increase removal efficiency and to minimize waste productivity. Radioactivity concentration of effluent is decreased from 0.01 Bq/mL to ND level. Besides, waste production was reduced from 15 drums/yr to 2 drums/yr (87%).

  10. A comprehensive centralized control system for radiation waste treatment facility

    International Nuclear Information System (INIS)

    Kong Jinsong

    2014-01-01

    A comprehensive centralized control system is designed for the radiation waste treatment facility that lacking of coordinated operational mechanism for the radiation waste treatment. The centralized control and alarm linkage of various systems is implemented to ensure effectively the safety of nuclear facility and materials, improve the integral control ability through advanced informatization ways. (author)

  11. Development of an Alternative Treatment Scheme for Sr/TRU Removal: Permanganate Treatment of AN-107 Waste

    International Nuclear Information System (INIS)

    Hallen, R.T.; Bryan, S.A.; Hoopes, F.V.

    2000-01-01

    A number of Hanford tanks received waste containing organic complexants, which increase the volubility of Sr-90 and transuranic (TRU) elements. Wastes from these tanks require additional pretreatment to remove Sr-90 and TRU for immobilization as low activity waste (Waste Envelope C). The baseline pretreatment process for Sr/TRU removal was isotopic exchange and precipitation with added strontium and iron. However, studies at both Battelle and Savannah River Technology Center (SRTC) have shown that the Sr/Fe precipitates were very difficult to filter. This was a result of the formation of poor filtering iron solids. An alternate treatment technology was needed for Sr/TRU removal. Battelle had demonstrated that permanganate treatment was effective for decontaminating waste samples from Hanford Tank SY-101 and proposed that permanganate be examined as an alternative Sr/TRU removal scheme for complexant-containing tank wastes such as AW107. Battelle conducted preliminary small-scale experiments to determine the effectiveness of permanganate treatment with AN-107 waste samples that had been archived at Battelle from earlier studies. Three series of experiments were performed to evaluate conditions that provided adequate Sr/TRU decontamination using permanganate treatment. The final series included experiments with actual AN-107 diluted feed that had been obtained specifically for BNFL process testing. Conditions that provided adequate Sr/TRU decontamination were identified. A free hydroxide concentration of 0.5M provided adequate decontamination with added Sr of 0.05M and permanganate of 0.03M for archived AN-107. The best results were obtained when reagents were added in the sequence Sr followed by permanganate with the waste at ambient temperature. The reaction conditions for Sr/TRU removal will be further evaluated with a 1-L batch of archived AN-107, which will provide a large enough volume of waste to conduct crossflow filtration studies (Hallen et al. 2000a)

  12. Development of an Alternative Treatment Scheme for Sr/TRU Removal: Permanganate Treatment of AN-107 Waste

    Energy Technology Data Exchange (ETDEWEB)

    RT Hallen; SA Bryan; FV Hoopes

    2000-08-04

    A number of Hanford tanks received waste containing organic complexants, which increase the volubility of Sr-90 and transuranic (TRU) elements. Wastes from these tanks require additional pretreatment to remove Sr-90 and TRU for immobilization as low activity waste (Waste Envelope C). The baseline pretreatment process for Sr/TRU removal was isotopic exchange and precipitation with added strontium and iron. However, studies at both Battelle and Savannah River Technology Center (SRTC) have shown that the Sr/Fe precipitates were very difficult to filter. This was a result of the formation of poor filtering iron solids. An alternate treatment technology was needed for Sr/TRU removal. Battelle had demonstrated that permanganate treatment was effective for decontaminating waste samples from Hanford Tank SY-101 and proposed that permanganate be examined as an alternative Sr/TRU removal scheme for complexant-containing tank wastes such as AW107. Battelle conducted preliminary small-scale experiments to determine the effectiveness of permanganate treatment with AN-107 waste samples that had been archived at Battelle from earlier studies. Three series of experiments were performed to evaluate conditions that provided adequate Sr/TRU decontamination using permanganate treatment. The final series included experiments with actual AN-107 diluted feed that had been obtained specifically for BNFL process testing. Conditions that provided adequate Sr/TRU decontamination were identified. A free hydroxide concentration of 0.5M provided adequate decontamination with added Sr of 0.05M and permanganate of 0.03M for archived AN-107. The best results were obtained when reagents were added in the sequence Sr followed by permanganate with the waste at ambient temperature. The reaction conditions for Sr/TRU removal will be further evaluated with a 1-L batch of archived AN-107, which will provide a large enough volume of waste to conduct crossflow filtration studies (Hallen et al. 2000a).

  13. Investigations on the treatment of waste waters from pig breeding

    Energy Technology Data Exchange (ETDEWEB)

    Cute, E; Mambet, E; Juriari, E; Murgoci, C

    1967-01-01

    The introduction of intensive methods of pig breeding has caused changes in the characteristics, particularly the strength, of the piggeries waste waters; analytical data are tabulated for waste waters from 3 pig-breeding farms and 1 large pig-breeding combine in Romania. At older piggeries, waste waters are treated by sedimentation and sludge digestion in Imhoff tanks. In more recent establishments, treatment comprises primary sedimentation followed by storage of the settled waste waters in ponds to be used for irrigation, and separate digestion of sludge in open tanks. Experiments showed that precautions are necessary to prevent blocking of the sewerage system by easily-settleable material before reaching the sedimentation tanks; sedimentation is more efficient in horizontal sedimentation tanks than in the older Imhoff tanks; biological treatment is possible without addition of nutrients, but the waste waters must be diluted; and digestion requires a longer period than that for sewage sludge, difficulties being caused by the presence of coarse suspended particles of waste feeding stuffs.

  14. Treatment of mixed radioactive liquid wastes at Argonne National Laboratory

    International Nuclear Information System (INIS)

    Vandegrift, G.F.; Chamberlain, D.B.; Conner, C.

    1994-01-01

    Aqueous mixed waste at Argonne National Laboratory (ANL) is traditionally generated in small volumes with a wide variety of compositions. A cooperative effort at ANL between Waste Management (WM) and the Chemical Technology Division (CMT) was established, to develop, install, and implement a robust treatment operation to handle the majority of such wastes. For this treatment, toxic metals in mixed-waste solutions are precipitated in a semiautomated system using Ca(OH) 2 and, for some metals, Na 2 S additions. This step is followed by filtration to remove the precipitated solids. A filtration skid was built that contains several filter types which can be used, as appropriate, for a variety of suspended solids. When supernatant liquid is separated from the toxic-metal solids by decantation and filtration, it will be a low-level waste (LLW) rather than a mixed waste. After passing a Toxicity Characteristic Leaching Procedure (TCLP) test, the solids may also be treated as LLW

  15. Content and Formation Cause of VOCs in Medical Waste Non-incineration Treatment Project

    Science.gov (United States)

    Dengchao, Jin; Hongjun, Teng; Zhenbo, Bao; Yang, Li

    2018-02-01

    When medical waste is treated by non-incineration technology, volatile organic compounds in the waste will be volatile out and form odor pollution. This paper studied VOCs productions in medical waste steam treatment project, microwave treatment project and chemical dinifection project. Sampling and analysis were carried out on the waste gas from treatment equipment and the gas in treatment workshop. The contents of nine VOCs were determined. It was found that the VOCs content in the exhaust gas at the outlet of steam treatment unit was much higher than that of microwave and chemical treatment unit, while the content of VOCs in the chemical treatment workshop was higher than that in the steam and microwave treatment workshop. The formation causes of VOCs were also analyzed and discussed in this paper.

  16. Super-compactor and grouting. Efficient and safe treatment of nuclear waste

    International Nuclear Information System (INIS)

    Li, Hongyou; Starke, Holger; Muetzel, Wolfgang; Winter, Marc

    2014-01-01

    The conditioning and volume reduction of nuclear waste are increasingly important factors throughout the world. Efficient and safe treatment of nuclear waste therefore plays a decisive role. Babcock Noell designed, manufactured and supplied a complete waste treatment facility for conditioning of the solid radioactive waste of a nuclear power plant to China. This facility consists of a Sorting Station, a Super-Compactor, a Grouting Unit with Capping Device and other auxiliary equipment which is described in more detail in the following article. This article gives an overview of the efficient and safe treatment of nuclear waste. Babcock Noell is a subsidiary of the Bilfinger Power Systems and has 40 years of experience in the field of design, engineering, construction, static and dynamic calculations, manufacturing, installation, commissioning, as well as in the service and operation of a wide variety of nuclear components and facilities worldwide.

  17. Treatment of Radioactive Contaminated Soil and Concrete Wastes Using the Regulatory Clearance

    Energy Technology Data Exchange (ETDEWEB)

    Kang, Il Sik; Ryu, W. S.; Kim, T. K.; Shon, J. S.; Ahn, S. J.; Lee, Y. H.; Bae, S. M.; Hong, D. S.; Ji, Y. Y.; Lee, B. C

    2008-11-15

    In the radioactive waste storage facilities at the Korea Atomic Energy Research Institute (KAERI) in Daejoen, there are thousands drums of radioactive contaminated soil and concrete wastes. The soil and concrete wastes were generated in 1988 during the decommissioning process of the research reactor and the attached radioactive waste treatment facility which were located in Seoul. The wastes were transported to Daejeon and have been stored since then. At the generation time, the radioactive contamination of the wastes was very low, and the radionuclides in the wastes was Co-60 and Cs-137. As the wastes have been stored for more than 20 years, the radioactivity concentration of the wastes has been decayed to become very extremely low. The wastes are needed to be treated because they take up large spaces at the storage facility. Also by treating the wastes, final disposal cost can be saved. So, the regulatory clearance was considered as a treatment method for the soil and concrete wastes with extremely low radioactivity concentration.

  18. Regulatory Support of Treatment of Savannah River Site Purex Waste

    International Nuclear Information System (INIS)

    Reid, L.T.

    2009-01-01

    This paper describes the support given by federal and state regulatory agencies to Savannah River Site (SRS) during the treatment of an organic liquid mixed waste from the Plutonium Extraction (Purex) process. The support from these agencies allowed (SRS) to overcome several technical and regulatory barriers and treat the Purex waste such that it met LDR treatment standards. (authors)

  19. Cermet high level waste forms: a pregress report

    International Nuclear Information System (INIS)

    Aaron, W.S.; Quinby, T.C.; Kobisk, E.H.

    1978-06-01

    The fixation of high level radioactive waste from both commercial and DOE defense sources as cermets is currently under study. This waste form consists of a continuous iron-nickel base metal matrix containing small particles of fission product oxides. Preliminary evaluations of cermets fabricated from a variety of simulated wastes indicate they possess properties providing advantages over other waste forms presently being considered, namely thermal conductivity, waste loading levels, and leach resistance. This report describes the progress of this effort, to date, since its initiation in 1977

  20. External versus internal fixation for bicondylar tibial plateau fractures: systematic review and meta-analysis.

    Science.gov (United States)

    Metcalfe, David; Hickson, Craig J; McKee, Lesley; Griffin, Xavier L

    2015-12-01

    It is uncertain whether external fixation or open reduction internal fixation (ORIF) is optimal for patients with bicondylar tibial plateau fractures. A systematic review using Ovid MEDLINE, Embase Classic, Embase, AMED, the Cochrane Library, Open Grey, Orthopaedic Proceedings, WHO International Clinical Trials Registry Platform, Current Controlled Trials, US National Institute for Health Trials Registry, and the Cochrane Central Register of Controlled Trials. The search was conducted on 3rd October 2014 and no language limits were applied. Inclusion criteria were all clinical study designs comparing external fixation with open reduction internal fixation of bicondylar tibial plateau fractures. Studies of only one treatment modality were excluded, as were those that included unicondylar tibial plateau fractures. Treatment effects from studies reporting dichotomous outcomes were summarised using odds ratios. Continuous outcomes were converted to standardized mean differences to assess the treatment effect, and inverse variance methods used to combine data. A fixed effect model was used for meta-analyses. Patients undergoing external fixation were more likely to have returned to preinjury activities by six and twelve months (P = 0.030) but not at 24 months follow-up. However, external fixation was complicated by a greater number of infections (OR 2.59, 95 % CI 1.25-5.36, P = 0.01). There were no statistically significant differences in the rates of deep infection, venous thromboembolism, compartment syndrome, or need for re-operation between the two groups. Although external fixation and ORIF are associated with different complication profiles, both are acceptable strategies for managing bicondylar tibial plateau fractures.

  1. US DOE Initiated Performance Enhancements to the Hanford Waste Treatment and Immobilization Plant (WTP) Low-activity Waste Vitrification (LAW) System

    International Nuclear Information System (INIS)

    Hamel, William F.; Gerdes, Kurt D.; Holton, Langdon K.; Pegg, Ian L.; Bowen, Brad W.

    2006-01-01

    The U.S Department of Energy Office of River Protection (DOE-ORP) is constructing a Waste Treatment and Immobilization Plant (WTP) for the treatment and vitrification of underground tank wastes stored at the Hanford Site in Washington State. The WTP comprises four major facilities: a pretreatment facility to separate the tank waste into high level waste (HLW) and low-activity waste (LAW) process streams, a HLW vitrification facility to immobilize the HLW fraction; a LAW vitrification facility to immobilize the LAW fraction, and an analytical laboratory to support the operations of all four treatment facilities. DOE has established strategic objectives to optimize the performance of the WTP facilities and the LAW and HLW waste forms to reduce the overall schedule and cost for treatment and vitrification of the Hanford tank wastes. This strategy has been implemented by establishing performance expectations in the WTP contract for the facilities and waste forms. In addition, DOE, as owner-operator of the WTP facilities, continues to evaluate (1) the design, to determine the potential for performance above the requirements specified in the WTP contract; and (2) improvements in production of the LAW and HLW waste forms. This paper reports recent progress directed at improving production of the LAW waste form. DOE's initial assessment, which is based on the work reported in this paper, is that the capacity of the WTP LAW vitrification facility can be increased by a factor of 2 to 4 with a combination of revised glass formulations, modest increases in melter glass operating temperatures, and a second-generation LAW melter with a larger surface area. Implementing these improvements in the LAW waste immobilization capability can benefit the LAW treatment mission by reducing both processing time and cost

  2. Discussion about the application of treatment process for dehydrated wet waste at nuclear power station

    International Nuclear Information System (INIS)

    Li Guanghua; Wu Qiang

    2009-01-01

    In nuclear power station, the most popular treatment about low level radioactive wet waste generated during the unit operating and maintenance is embedded by cement. For radioactive waste minimization, this article introduces a new treatment process to dehydrate and compress wet waste. According to the development and application of the treatment process for the wet waste, and comparing with the formerly treatment-the cement embedding, prove that the new treatment can meet the purpose for volume reduction of wet waste. (authors)

  3. AERE contracts with DOE on the treatment and disposal of Intermediate Level Wastes

    International Nuclear Information System (INIS)

    Partridge, B.A.

    1985-07-01

    Individual summaries are provided for each contract report, under the titles: comparative evaluation of α and βγ irradiated medium level waste forms; modelling and characterisation of intermediate level waste forms based on polymers; optimisation of processing parameters for polymer and bitumen modified cements; α damage in non-reference matrix materials; leaching mechanisms and modelling; inorganic ion exchange treatment of medium active effluents; electrical processes for the treatment of medium active liquid waste; fast reactor fuel element cladding; dissolver residues; effects of radiation on the properties of cemented MTR waste forms; equilibrium leach testing of cemented MTR waste forms; radiolytic oxidation of radionuclides; immobilisation of liquid organic wastes; quality control, non-conformances and corrective action; application of gel processes in the treatment of actinide-containing liquid wastes; the role of colloids in the release of radionuclides from nuclear waste. (author)

  4. Decommissioning Combustible Waste Treatment using Oxygen-Enriched Incinerator

    Energy Technology Data Exchange (ETDEWEB)

    Min, Byungyoun; Lee, Yoonji; Yun, Gyoungsu; Lee, Kiwon; Moon, Jeikwon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-05-15

    The aim of the paper is current status of treatment for the decommissioning combustible waste in KAERI and for the purpose of the volume reduction and clearance for decommissioning combustible wastes generated by the decommissioning projects. The incineration technology has been selected for the treatment of combustible wastes. About 34 tons of decommissioning combustible waste has been treated using Oxygen Enriched incineration. Temperature, pressure of major components, stack gas concentration, i. e., SOx, NOx, CO, CO{sub 2} and HCl, and the residual oxygen were measured. Measured major parameters during normal operation were sustained on a stable status within a criteria operation condition. Oxygen enriched air, 22vol. % (dry basis) was used for stable incineration. The volume reduction ratio has achieved about 1/117. The incineration with decommissioning radioactive combustible waste is possible with moderate oxygen enrichment of 22 vol.% (dry basis) into the supply air. The incineration facility operated quite smoothly through the analysis major critical parameters of off-gas. The pressure, off-gas flow and temperature of major components remained constant within the range specified. The measures gases and particulate materials in stack were considerably below the regulatory limits. The achieved volume reduction ratio through incineration is about 1/117.

  5. Waste treatment at the Radiochemical Engineering Development Center

    International Nuclear Information System (INIS)

    Brunson, R.R.; Bond, W.D.; Chattin, F.R.; Collins, R.T.; Sullivan, G.R.; Wiles, R.H.

    1997-01-01

    At the Radiochemical Engineering Development Center (REDC) irradiated targets are processed for the recovery of valuable radioisotopes, principally transuranium nuclides. A system was recently installed for treating the various liquid alkaline waste streams for removal of excess radioactive contaminants at the REDC. Radionuclides that are removed will be stored as solids and thus the future discharge of radionuclides to liquid low level waste tank storage will be greatly reduced. The treatment system is of modular design and is installed in a hot cell (Cubicle 7) in Building 7920 at the REDC where preliminary testing is in progress. The module incorporates the following: (1) a resorcinol-formaldehyde resin column for Cs removal, (2) a cross flow filtration unit for removal of rare earths and actinides as hydroxide, and (3) a waste solidification unit. Process flowsheets for operation of the module, key features of the module design, and its computer-assisted control system are presented. Good operability of the cross flow filter system is mandatory to the successful treatment of REDC wastes. Results of tests to date on the operation of the filter in its slurry collection mode and its slurry washing mode are presented. These tests include the effects of entrained organic solvent in the waste stream feed to the filter

  6. Argonne-West facility requirements for a radioactive waste treatment demonstration

    International Nuclear Information System (INIS)

    Dwight, C.C.; Felicione, F.S.; Black, D.B.; Kelso, R.B.; McClellan, G.C.

    1995-01-01

    At Argonne National Laboratory-West (ANL-W), near Idaho Falls, Idaho, facilities that were originally constructed to support the development of liquid-metal reactor technology are being used and/or modified to meet the environmental and waste management research needs of DOE. One example is the use of an Argonne-West facility to conduct a radioactive waste treatment demonstration through a cooperative project with Science Applications International Corporation (SAIC) and Lockheed Idaho Technologies Company. The Plasma Hearth Process (PBP) project will utilize commercially-adapted plasma arc technology to demonstrate treatment of actual mixed waste. The demonstration on radioactive waste will be conducted at Argonne's Transient Reactor Test Facility (TREAT). Utilization of an existing facility for a new and different application presents a unique set of issues in meeting applicable federal state, and local requirements as well as the additional constraints imposed by DOE Orders and ANL-W site requirements. This paper briefly describes the PHP radioactive demonstrations relevant to the interfaces with the TREAT facility. Safety, environmental design, and operational considerations pertinent to the PHP radioactive demonstration are specifically addressed herein. The personnel equipment, and facility interfaces associated with a radioactive waste treatment demonstration are an important aspect of the demonstration effort. Areas requiring significant effort in preparation for the PBP Project being conducted at the TREAT facility include confinement design, waste handling features, and sampling and analysis considerations. Information about the facility in which a radioactive demonstration will be conducted, specifically Argonne's TREAT facility in the case of PHP, may be of interest to other organizations involved in developing and demonstrating technologies for mixed waste treatment

  7. Treatment of complex electroplating waste by 'zero discharge' technique

    International Nuclear Information System (INIS)

    Khattak, B.Q.; Ram Sankar, P.; Jain, A.K.

    2009-01-01

    Surface treatment processes generate lot of liquid waste, which contains toxic substances and are potentially harmful to the living beings. It is extremely difficult to treat the pollutants where processes and frequencies are not fixed. In Chemical Treatment Facility of RRCAT, surface treatment processes are user dependent and makes the electroplating waste very complicated. Initially the waste was treated by simple chemical transformation technique in which heavy metal ions are converted to hydroxide precipitates. Non metallic ions that contribute much to the plating waste could not be treated by this process. To remove maximum possible pollutants, many experiments were conducted on the laboratory scale. Based on those results, a pilot ion exchange plant of various resins was introduced in the process to achieve disposal quality effluent. Anionic load of Phosphate, Nitrate and fluoride caused frequent anionic bed exhaustions and polymeric network damaging. To avoid this phenomenon a new setup was designed. This pre treatment has the capacity to treat 500 litres per hour connected to a platter with clarifier followed by high pressure carbon and pebbles filters. Analysis of these ions was carried out on the advanced ion chromatography system and is found free of toxic metals, phosphate and fluoride. This effluent can be reused by adding a reverse osmosis system followed by ion exchange system to produce good quality de mineralized water needed for surface treatment activities. In this paper we describe the existing status of effluent treatment facility and future plans for achieving 'zero discharge'. (author)

  8. Treatment of Waste Lubricating Oil by Chemical and Adsorption Process Using Butanol and Kaolin

    Science.gov (United States)

    Riyanto; Ramadhan, B.; Wiyanti, D.

    2018-04-01

    Treatment of waste lubricating oil by chemical and adsorption process using butanol and kaolin has been done. Quality of lubricating oil after treatment was analysis using Atomic Absorption Spectrophotometer (AAS) and Gas Chromatography-Mass Spectrometry (GC-MS). The effects of the treatment of butanol, KOH, and kaolin to metals contain in waste lubricating oil treatment have been evaluated. Treatment of waste lubricating oil has been done using various kaolin weight, butanol, and KOH solution. The result of this research show metal content of Ca, Mg, Pb, Fe and Cr in waste lubricating oil before treatment are 1020.49, 367.02, 16.40, 36.76 and 1,80 ppm, respectively. The metal content of Ca, Mg, Pb, Fe and Cr in the waste lubricating oil after treatment are 0.17, 9.85, 34.07, 78.22 and 1.20 ppm, respectively. The optimum condition for treatment of waste lubricating oil using butanol, KOH, and kaolin is 30 mL, 3.0 g and 1.5 g, respectively. Chemical and adsorption method using butanol and kaolin can be used for decrease of metals contain in waste lubricating oil.

  9. Capsule-Fixated Intraocular Lens Implantation in Small Pupil Cases.

    Science.gov (United States)

    Schojai, Merita; Schultz, Tim; Burkhard Dick, H

    2017-08-01

    To describe a new technique for implantation of capsule-fixated intraocular lenses (IOLs) (FEMTIS; Oculentis, Berlin, Germany) in patients with small pupils. In 4 eyes with small pupils, an anterior capsule-fixated IOL was implanted into the capsular bag after femtosecond laser treatment. The two large and two small flaps of the IOL were elevated to the front of the iris and the anterior capsule. Finally, the iris was flipped over the flaps to ensure a fixation of the capsule inside of the capsulotomy. In all cases, the implantation of anterior capsule-fixated IOLs was possible. No complications occurred during surgery or within the first months after surgery. With the described technique, capsulefixated IOLs can be implanted in eyes with small pupil easily and safely. This type of IOL has great potential to improve the refractive outcome by better prediction of the postoperative IOL position and eliminating IOL rotation after cataract surgery. [J Refract Surg. 2017;33(8):568-570.]. Copyright 2017, SLACK Incorporated.

  10. Membrane bioreactors for waste gas treatment.

    NARCIS (Netherlands)

    Reij, M.W.; Keurentjes, J.T.F.; Hartmans, S.

    1998-01-01

    This review describes the recent development of membrane reactors for biological treatment of waste gases. In this type of bioreactor gaseous pollutants are transferred through a membrane to the liquid phase, where micro-organisms degrade the pollutants. The membrane bioreactor combines the

  11. Membrane bioreactors for waste gas treatment

    NARCIS (Netherlands)

    Reij, M.W.; Keurentjes, J.T.F.; Hartmans, S.

    1998-01-01

    This review describes the recent development of membrane reactors for biological treatment of waste gases. In this type of bioreactor gaseous pollutants are transferred through a membrane to the liquid phase, where micro-organisms degrade the pollutants. The membrane bioreactor combines the

  12. Waste Treatment Plant Liquid Effluent Treatability Evaluation

    International Nuclear Information System (INIS)

    LUECK, K.J.

    2001-01-01

    Bechtel National, Inc. (BNI) provided a forecast of the radioactive, dangerous liquid effluents expected to be generated by the Waste Treatment Plant (WTP). The forecast represents the liquid effluents generated from the processing of 25 distinct batches of tank waste through the WTP. The WTP liquid effluents will be stored, treated, and disposed of in the Liquid Effluent Retention Facility (LERF) and the Effluent Treatment Facility (ETF). Fluor Hanford, Inc. (FH) evaluated the treatability of the WTP liquid effluents in the LERFIETF. The evaluation was conducted by comparing the forecast to the LERFIETF treatability envelope, which provides information on the items that determine if a liquid effluent is acceptable for receipt and treatment at the LERFIETF. The WTP liquid effluent forecast is outside the current LERFlETF treatability envelope. There are several concerns that must be addressed before the WTP liquid effluents can be accepted at the LERFIETF

  13. Toluene : biological waste-gas treatment, toxicity and microbial adaptation

    NARCIS (Netherlands)

    Weber, F.J.

    1995-01-01

    Due to the increasing stringent legislation concerning the emission of volatile organic compounds, there is nowadays a growing interest to apply biological waste-gas treatment techniques for the removal of higher concentrations of specific contaminants from waste gases. Fluctuations in the

  14. RADIOACTIVE DEMONSTRATION OF FINAL MINERALIZED WASTE FORMS FOR HANFORD WASTE TREATMENT PLANT SECONDARY WASTE BY FLUIDIZED BED STEAM REFORMING USING THE BENCH SCALE REFORMER PLATFORM

    Energy Technology Data Exchange (ETDEWEB)

    Crawford, C.; Burket, P.; Cozzi, A.; Daniel, W.; Jantzen, C.; Missimer, D.

    2012-02-02

    The U.S. Department of Energy's Office of River Protection (ORP) is responsible for the retrieval, treatment, immobilization, and disposal of Hanford's tank waste. Currently there are approximately 56 million gallons of highly radioactive mixed wastes awaiting treatment. A key aspect of the River Protection Project (RPP) cleanup mission is to construct and operate the Waste Treatment and Immobilization Plant (WTP). The WTP will separate the tank waste into high-level and low-activity waste (LAW) fractions, both of which will subsequently be vitrified. The projected throughput capacity of the WTP LAW Vitrification Facility is insufficient to complete the RPP mission in the time frame required by the Hanford Federal Facility Agreement and Consent Order, also known as the Tri-Party Agreement (TPA), i.e. December 31, 2047. Therefore, Supplemental Treatment is required both to meet the TPA treatment requirements as well as to more cost effectively complete the tank waste treatment mission. In addition, the WTP LAW vitrification facility off-gas condensate known as WTP Secondary Waste (WTP-SW) will be generated and enriched in volatile components such as {sup 137}Cs, {sup 129}I, {sup 99}Tc, Cl, F, and SO{sub 4} that volatilize at the vitrification temperature of 1150 C in the absence of a continuous cold cap (that could minimize volatilization). The current waste disposal path for the WTP-SW is to process it through the Effluent Treatment Facility (ETF). Fluidized Bed Steam Reforming (FBSR) is being considered for immobilization of the ETF concentrate that would be generated by processing the WTP-SW. The focus of this current report is the WTP-SW. FBSR offers a moderate temperature (700-750 C) continuous method by which WTP-SW wastes can be processed irrespective of whether they contain organics, nitrates, sulfates/sulfides, chlorides, fluorides, volatile radionuclides or other aqueous components. The FBSR technology can process these wastes into a crystalline

  15. Research on monitoring and management information integration technique in waste treatment and management

    International Nuclear Information System (INIS)

    Kong Jinsong; Yu Ren; Mao Wei

    2013-01-01

    The integration of the waste treatment process and the device status monitoring information and management information is a key problem required to be solved in the information integration of the waste treatment and management. The main content of the monitoring and management information integration is discussed in the paper. The data exchange techniques, which are based on the OPC, FTP and data push technology, are applied to the different monitoring system respectively, according to their development platform, to realize the integration of the waste treatment process and device status monitoring information and management information in a waste treatment center. (authors)

  16. Mixed Waste Focus Area Mercury Working Group: An integrated approach to mercury waste treatment and disposal

    International Nuclear Information System (INIS)

    Conley, T.B.; Morris, M.I.; Osborne-Lee, I.W.

    1998-03-01

    In May 1996, the US Department of Energy (DOE) Mixed Waste Focus Area (MWFA) initiated the Mercury Working Group (HgWG). The HgWG was established to address and resolve the issues associated with mercury contaminated mixed wastes. During the MWFA's initial technical baseline development process, three of the top four technology deficiencies identified were related to the need for amalgamation, stabilization, and separation removal technologies for the treatment of mercury and mercury contaminated mixed waste. The HgWG is assisting the MWFA in soliciting, identifying, initiating, and managing efforts to address these areas. The focus of the HgWG is to better establish the mercury related treatment technologies at the DOE sites, refine the MWFA technical baseline as it relates to mercury treatment, and make recommendations to the MWFA on how to most effectively address these needs. Based on the scope and magnitude of the mercury mixed waste problem, as defined by HgWG, solicitations and contract awards have been made to the private sector to demonstrate both the amalgamation and stabilization processes using actual mixed wastes. Development efforts are currently being funded that will address DOE's needs for separation removal processes. This paper discusses the technology selection process, development activities, and the accomplishments of the HgWG to date through these various activities

  17. Staple fixation for akin proximal phalangeal osteotomy in the treatment of hallux valgus interphalangeus.

    Science.gov (United States)

    Neumann, Julie A; Reay, Kathleen D; Bradley, Kendall E; Parekh, Selene G

    2015-04-01

    The Akin proximal phalangeal osteotomy is commonly used in conjunction with metatarsal osteotomies to treat hallux valgus. Multiple fixation methods including suture, wire, screw, and staple fixation have been described. The aims of this study were to assess the intraoperative and postoperative complications and to evaluate short-term postoperative outcomes in patients who underwent Akin osteotomy with staple fixation. Forty-four patients (51 feet) with painful hallux valgus were retrospectively reviewed at an average of 40.4 ± 15.8 (range, 25.9 to 79.9) weeks following an Akin osteotomy with staple fixation. Patient reported preoperative and postoperative Visual Analog Score (VAS) (0 to 10, 0 = no pain) was recorded. Level of activity was reported postoperatively. Hallux valgus angles (HVAs), intermetatarsal angles (IMAs), and hallux valgus interphalangeus angles (IPAs) were evaluated on preoperative as well as final postoperative radiographs. Postoperative clinical and radiographic examinations were used to evaluate for complications. Mean VAS improved from 4.4 ± 2.6 to 1.0 ± 1.2 (P hallux valgus correction with improvement in pain and hallux valgus deformity with a low risk for complications. Level IV, case series. © The Author(s) 2014.

  18. Integrated process analysis of treatment systems for mixed low level waste

    International Nuclear Information System (INIS)

    Cooley, C.R.; Schwinkendorf, W.E.; Bechtold, T.E.

    1997-10-01

    Selection of technologies to be developed for treatment of DOE's mixed low level waste (MLLW) requires knowledge and understanding of the expected costs, schedules, risks, performance, and reliability of the total engineered systems that use these technologies. Thus, an integrated process analysis program was undertaken to identify the characteristics and needs of several thermal and nonthermal systems. For purposes of comparison, all systems were conceptually designed for a single facility processing the same amount of waste at the same rate. Thirty treatment systems were evaluated ranging from standard incineration to innovative thermal systems and innovative nonthermal chemical treatment. Treating 236 million pounds of waste in 20 years through a central treatment was found to be the least costly option with total life cycle cost ranging from $2.1 billion for a metal melting system to $3.9 billion for a nonthermal acid digestion system. Little cost difference exists among nonthermal systems or among thermal systems. Significant cost savings could be achieved by working towards maximum on line treatment time per year; vitrifying the final waste residue; decreasing front end characterization segregation and sizing requirements; using contaminated soil as the vitrifying agent; and delisting the final vitrified waste form from Resource Conservation and Recovery Act (RCRA) Land Disposal Restriction (LDR) requirements

  19. Closed Fuel Cycle Waste Treatment Strategy

    Energy Technology Data Exchange (ETDEWEB)

    Vienna, J. D. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Collins, E. D. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Crum, J. V. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Ebert, W. L. [Argonne National Lab. (ANL), Argonne, IL (United States); Frank, S. M. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Garn, T. G. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Gombert, D. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Jones, R. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Jubin, R. T. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Maio, V. C. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Marra, J. C. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Matyas, J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Nenoff, T. M. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Riley, B. J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Sevigny, G. J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Soelberg, N. R. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Strachan, D. M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Thallapally, P. K. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Westsik, J. H. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2015-02-01

    This study is aimed at evaluating the existing waste management approaches for nuclear fuel cycle facilities in comparison to the objectives of implementing an advanced fuel cycle in the U.S. under current legal, regulatory, and logistical constructs. The study begins with the Global Nuclear Energy Partnership (GNEP) Integrated Waste Management Strategy (IWMS) (Gombert et al. 2008) as a general strategy and associated Waste Treatment Baseline Study (WTBS) (Gombert et al. 2007). The tenets of the IWMS are equally valid to the current waste management study. However, the flowsheet details have changed significantly from those considered under GNEP. In addition, significant additional waste management technology development has occurred since the GNEP waste management studies were performed. This study updates the information found in the WTBS, summarizes the results of more recent technology development efforts, and describes waste management approaches as they apply to a representative full recycle reprocessing flowsheet. Many of the waste management technologies discussed also apply to other potential flowsheets that involve reprocessing. These applications are occasionally discussed where the data are more readily available. The report summarizes the waste arising from aqueous reprocessing of a typical light-water reactor (LWR) fuel to separate actinides for use in fabricating metal sodium fast reactor (SFR) fuel and from electrochemical reprocessing of the metal SFR fuel to separate actinides for recycle back into the SFR in the form of metal fuel. The primary streams considered and the recommended waste forms include; Tritium in low-water cement in high integrity containers (HICs); Iodine-129: As a reference case, a glass composite material (GCM) formed by the encapsulation of the silver Mordenite (AgZ) getter material in a low-temperature glass is assumed. A number of alternatives with distinct advantages are also considered including a fused silica waste form

  20. Radioactive waste treatment

    International Nuclear Information System (INIS)

    Alter, U.

    1988-01-01

    For the Federal Government the safe disposal of waste from nuclear power plants constitutes the precondition for their further operation. The events in the year 1987 about the conditioning and transport of low activity waste and medium activity waste made it clear that it was necessary to intensify state control and to examine the structures in the field of waste disposal. A concept for the control of radioactive waste with negligible heat development (LAW) from nuclear installations is presented. (DG) [de