WorldWideScience

Sample records for research pilot plant

  1. Waste water pilot plant research, development, and demonstration permit application

    International Nuclear Information System (INIS)

    1993-03-01

    This permit application has been prepared to obtain a research, development, and demonstration permit to perform pilot-scale treatability testing on the 242-A Evaporator process condensate waste water effluent stream. It provides the management framework, and controls all the testing conducted in the waste water pilot plant using dangerous waste. It also provides a waste acceptance envelope (upper limits for selected constituents) and details the safety and environmental protection requirements for waste water pilot plant testing. This permit application describes the overall approach to testing and the various components or requirements that are common to all tests. This permit application has been prepared at a sufficient level of detail to establish permit conditions for all waste water pilot plant tests to be conducted

  2. Kvanefjeld refinery pilot plant operations

    International Nuclear Information System (INIS)

    Krebs, Damien; Furfaro, Domenic

    2016-01-01

    Greenland Minerals and Energy is a junior project development company which is listed on the Australian Stock Exchange (asx:GGG). It is developing the Kvanefjeld rare earth and uranium project located in the southern tip of Greenland. The project has completed a Feasibility Study and is currently in the permitting phase. Last year was a busy time for the company as it completed a Feasibility Study, a mining licence application (draft submitted in December 2015) and pilot plant operations. Beneficiation pilot plant operations were completed at GTK in Finland in April 2015. This pilot plant treated approximately 30 tonnes of ore to producing almost 2 tonnes of rare earth mineral concentrate. Later in the year a hydrometallurgical pilot plant was performed which mimicked the Refinery process. This pilot plant was performed at Outotec’s Pori Research laboratories in Finland from September till October 2015. The pilot plant treated approximately 200 kilograms of concentrate over 4 split operating campaigns. Each campaign was performed to focus on the performance of a specific part of the refinery flowsheet. This allowed for full operating focus on a single unit operation to ensure that it was operating correctly. The pilot plant operations were quite successful with no major issues with the flowsheet identified through continuous operation. Some fine tuning of conditions was required to ensure adequate removal of impurities was performed with recycle streams incorporated. Overall the leach extractions observed in the pilot plant exceeded the design assumptions in the Feasibility Study. These programs were partially funded by the EURARE program. The EURARE program aims to encourage the sustainable development of European based rare earth projects. This has the goal of allowing Europe to become less reliant on importation of these key raw materials. The professionalism and performance of both GTK and Outotec contributed significantly to the success of the pilot plant

  3. Pilot plant study

    International Nuclear Information System (INIS)

    Morris, M.E.

    1978-01-01

    Sandia Laboratories undertook the design and fabrication of an 8 ton/day dry sewage sludge irradiatior. The facility is intended (1) to function as a high-gamma-dose rate research facility; (2) to be a testbed for the unique electrical and mechanical components to be used in larger facilities; (3) to fulfill the formal requirements of a pilot plant so that design and construction of a demonstration facility could proceed; and (4) to provide accurate data base on construction and operating experience for the Environmental Impact Assessment (EIA), the Safety Analysis Report (SAR), and the cost analyses for a larger facility. The facility and its component systems are described in detail

  4. Results of the DIOS pilot plant test and summary of the joint research; DIOS pilot plant no shiken sogyo kekka to kenkyu seika no matome

    Energy Technology Data Exchange (ETDEWEB)

    Sugiyama, T [Center for Coal Utilization, Japan, Tokyo (Japan); Kawaoka, K [The Japan Iron and Steel Federation, Tokyo (Japan)

    1996-09-01

    A joint research had been carried out with a subsidy from the Agency of Natural Resources and Energy since fiscal 1988 to fiscal 1995 on the direct iron ore smelting reduction process (DIOS process). The process utilizes coal directly as a process to use the strong points and supplement the weak points of the blast furnace process. During the period, a pilot plant had been operated since 1993. Upon having completed the feasibility study, this paper reports the result thereof. The main facilities consist of a smelting and reducing furnace of iron bath type, a spare reducing furnace of fluidized bed type, and a preheating furnace. The former two furnaces constitute a unit structure with the two furnaces connected vertically. The pilot plant achieved a three-day continuous operation producing 500 tons of iron every day. The production rate reached 21 tons an hour at an upward oxygen blowing velocity of about 13,000 Nm {sup 3} per hour. The coal unit requirement showed a result of <1000 kg/t for high VM coal and <900 kg/t for low VM coal. These results verified a possibility that this process can supplement or replace the blast furnace process even for a production scale of 9000 tons a day. 7 refs., 15 figs., 3 tabs.

  5. Pilot-scale Biogas Plant for the Research and Development of New Technologies

    Directory of Open Access Journals (Sweden)

    Ivan Simeonov

    2012-09-01

    Full Text Available Тhe paper describes a new pilot-scale biogas plant of the Institute of Microbiology - Bulgarian Academy of Sciences. The equipment includes: a 100 L pilot bioreactor, a 200 L metal gasholder, sensors, actuators, a two-level automatic process monitoring and control system, a fire and explosion protection system and two web cameras. The monitoring and control system is composed on the lower level of a controller Beckhoff, and on the higher level - of a PC with specialized software (under development. The pilot biogas plant is designed to work out and scale up various anaerobic digestion (AD technologies based on different types of feedstock. All the data will be stored on the PC for quick reference and possibly data mining, parameter identification and verification of different AD mathematical models.

  6. The Marcoule pilot plant

    International Nuclear Information System (INIS)

    Faugeras, P.; Calame Longjean, A.; Le Bouhellec, J.; Revol, G.

    1986-06-01

    The Marcoule spent fuel reprocessing pilot facility was built in 1960-1961 for extended testing of the PUREX process with various types of fuel under conditions similar to those encountered in a production plant. Extensive modification work was undertaken on the facility in 1983 in the scope of the TOR project, designed with the following objectives: - increase the throughput capacity to at least 5 metric tons of PHENIX equivalent fuel per year, - extend equipment and process R and D capability, - improve job safety by maximum use of remote handling facilities, - maximize waste conditioning treatments to produce waste forms suitable for direct storage, - provide a true industrial process demonstration in continuous operation under centralized control using computerized procedures. The redesigned plant is scheduled to begin operation during the second half of 1986. The proximity of the Industrial Prototypes Service and the ATALANTE radiochemical research laboratory scheduled to begin operation in 1990, will provide a synergistic environment in which R and D program may be carried out under exceptional conditions

  7. Actinide chemistry research supporting the Waste Isolation Pilot Plant (WIPP): FY94 results

    Energy Technology Data Exchange (ETDEWEB)

    Novak, C.F. [ed.

    1995-08-01

    This document contains six reports on actinide chemistry research supporting the Waste Isolation Pilot Plant (WIPP). These reports, completed in FY94, are relevant to the estimation of the potential dissolved actinide concentrations in WIPP brines under repository breach scenarios. Estimates of potential dissolved actinide concentrations are necessary for WIPP performance assessment calculations. The specific topics covered within this document are: the complexation of oxalate with Th(IV) and U(VI); the stability of Pu(VI) in one WIPP-specific brine environment both with and without carbonate present; the solubility of Nd(III) in a WIPP Salado brine surrogate as a function of hydrogen ion concentration; the steady-state dissolved plutonium concentrations in a synthetic WIPP Culebra brine surrogate; the development of a model for Nd(III) solubility and speciation in dilute to concentrated sodium carbonate and sodium bicarbonate solutions; and the development of a model for Np(V) solubility and speciation in dilute to concentrated sodium Perchlorate, sodium carbonate, and sodium chloride media.

  8. Actinide chemistry research supporting the Waste Isolation Pilot Plant (WIPP): FY94 results

    International Nuclear Information System (INIS)

    Novak, C.F.

    1995-08-01

    This document contains six reports on actinide chemistry research supporting the Waste Isolation Pilot Plant (WIPP). These reports, completed in FY94, are relevant to the estimation of the potential dissolved actinide concentrations in WIPP brines under repository breach scenarios. Estimates of potential dissolved actinide concentrations are necessary for WIPP performance assessment calculations. The specific topics covered within this document are: the complexation of oxalate with Th(IV) and U(VI); the stability of Pu(VI) in one WIPP-specific brine environment both with and without carbonate present; the solubility of Nd(III) in a WIPP Salado brine surrogate as a function of hydrogen ion concentration; the steady-state dissolved plutonium concentrations in a synthetic WIPP Culebra brine surrogate; the development of a model for Nd(III) solubility and speciation in dilute to concentrated sodium carbonate and sodium bicarbonate solutions; and the development of a model for Np(V) solubility and speciation in dilute to concentrated sodium Perchlorate, sodium carbonate, and sodium chloride media

  9. Process Experimental Pilot Plant

    International Nuclear Information System (INIS)

    Henze, H.

    1986-01-01

    The Process Experimental Pilot Plant (PREPP) at the Idaho National Engineering Laboratory (INEL) was built to convert transuranic contaminated solid waste into a form acceptable for disposal at the Waste Isolation Pilot Plant (WIPP), located near Carlsbad, New Mexico. There are about 2.0 million cubic ft of transuranic waste stored at the Transuranic Storage Area of the INEL's Radioactive Waste Management Complex (RWMC). The Stored Waste Examination Pilot Plant (SWEPP) located at the RWMC will examine this stored transuranic waste to determine if the waste is acceptable for direct shipment to and storage at WIPP, or if it requires shipment to PREPP for processing before shipment to WIPP. The PREPP process shreds the waste, incinerates the shredded waste, and cements (grouts) the shredded incinerated waste in new 55-gal drums. Unshreddable items are repackaged and returned to SWEPP. The process off-gas is cleaned prior to its discharge to the atmosphere, and complies with the effluent standards of the State of Idaho, EPA, and DOE. Waste liquid generated is used in the grouting operation

  10. Research cooperation project on environmentally friendly technology for highly efficient mineral resources extraction and treatment. Detail design for pilot plant (Mechanical fabrication)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-03-01

    The paper prepared plans of the mechanical equipment in the detailed design of a pilot plant in the joint research project on the environmental protection technology for highly efficient mineral resource extraction and treatment. (NEDO)

  11. Development of charcoal retort pilot plant in Zambia. African Energy Programme research report series no. 4

    International Nuclear Information System (INIS)

    Yamba, F.D.

    1988-01-01

    . The latter is to ensure that effective combustion takes place in the furnace. For the purpose of condensing smoke, emanating from the retort chamber, into a pyroligenous liquor, a heat exchanger is designed. During the design, most of the parameters which were unknown from theoretical consideration, were obtained from experimental analysis of the retort model. Finally, based on actual costs of materials for construction of the pilot plant, including buildings, a financial analysis of the pilot plant is undertaken. The analysis indicates that a second version of two retort chambers of 10m 3 each being supplied with heat from one furnace is economically attractive. Further improvement in the financial analysis is obtained through sale of both charcoal and pyroligenous liquor. It is recommended that construction of the plant be completed, vigorously tested and commissioned before commercialisation can be undertaken. (author)

  12. Waste Isolation Pilot Plant Overview

    Energy Technology Data Exchange (ETDEWEB)

    Weaver, Douglas James [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2017-03-27

    The mission of Waste Isolation Pilot Plant (WIPP) is to demonstrate the safe, environmentally sound, cost effective, permanent disposal of Transuranic (TRU) waste left from production of nuclear weapons.

  13. WIPP: Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    1984-01-01

    The following aspects of the Waste Isolation Pilot Plant are discussed briefly: history and site selection; salt as a disposal medium; transporting waste materials; early key events; impacts on New Mexico; project organization; and site certification profile

  14. Research cooperation project on environmentally friendly technology for highly efficient mineral resources extraction and treatment. Detail design for pilot plant

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-03-01

    Photographs and drawings were edited into a book in relation with a joint project for environment preservation technologies in high-efficiency extraction and treatment of mineral resources, and detail design for a pilot plant. The book classified the related devices into fabricated devices, purchased devices and electrical devices, and contains detailed drawings and photographs thereof. (NEDO)

  15. Development of 1000kW-class MCFC pilot plant

    Energy Technology Data Exchange (ETDEWEB)

    Ooue, M.; Yasue, H. [MCFC Research Association, Mie (Japan); Takasu, K.; Tsuchitori, T.

    1996-12-31

    This pilot plant is a part of the New Sunshine Program which has proceeded by the Agency of Industrial Science and Technology of the Ministry of International Trade and Industry. MCFC Research Association is entrusted with the development of the pilot plant, and constructing it at Kawagoe site. Following items will be verified by this pilot plant operation. (a) Development of 250kW class stack and confirmation of stack performance and decay rate. (b) System verification such as basic process, control system and operation characteristics, toward commercialization. (c) To get design data for demonstration plant.

  16. The ten stages pilot plant: its utilization in the research of the dynamic behavior and regullating process of a jet nozzle cascade for uranium enrichment

    International Nuclear Information System (INIS)

    Yadoya, R.; Camara, A.S.; Consiglio, R.V.; Bley, P.; Hein, H.; Linder, G.

    1986-01-01

    A ten stage pilot plant to study experimentally dynamic behavior of a uranium enrichment plant based on separation nozzle process was developed and constructed at Karlsruhe Nuclear Research Center. This installation was transfered to the Development Center of Nuclear Technology (CDTN) of Nuclebras in Belo Horizonte, Brazil. The separation elements installed have a new design with higher efficiency, Known as double-deflections system. The power plant has been used to improve the control method and to prove the stability of separation nozzle cascade under pertubations produced artificially. The stabilization process of UF 6 quantity in cascade by UF 6 inventory regulation at bottom stage will have practication in the First Cascade, in Rezende, RJ, Brazil and may be uded i emonstration plant. The experimental results have shown to be comparable with those obtained by computer simulation. (Author) [pt

  17. Decommissioning of an uranium hexafluoride pilot plant

    International Nuclear Information System (INIS)

    Santos, Ivan; Abrao, Alcidio; Carvalho, Fatima M.S.; Ayoub, Jamil M.S.

    2009-01-01

    The Institute of Nuclear and Energetic Researches has completed fifty years of operation, belongs to the National Commission for Nuclear Energy, it is situated inside the city of Sao Paulo. The IPEN-CNEN/SP is a Brazilian reference in the nuclear fuel cycle, researches in this field began in 1970, having dominance in the cycle steps from Yellow Cake to Uranium Hexafluoride technology. The plant of Uranium Hexafluoride produced 35 metric tonnes of this gas by year, had been closed in 1992, due to domain and total transference of know-how for industrial scale, demand of new facilities for the improvement of recent researches projects. The Institute initiates decommissioning in 2002. Then, the Uranium Hexafluoride pilot plant, no doubt the most important unit of the fuel cycle installed at IPEN-CNEN/SP, beginning decommissioning and dismantlement (D and D) in 2005. Such D and D strategies, planning, assessment and execution are described, presented and evaluated in this paper. (author)

  18. Extractive metalurgical pilot plant. Project and installation

    International Nuclear Information System (INIS)

    Paula, H.C.B.; Rolim, T.L.; Santana, A.O. de; Santos, F.S.M. dos; Dantas, C.C.

    1986-01-01

    An extractive metalurgical pilot plant with a flow capacity of 200l/h of phosphoric leach, recovering 80% of the uranium content has been designed and installed. Starting from the diagrams of the chemical process in the laboratory scale, the equipment worksheet of the basic project were developed. The procedure for dimensioning and positioning of each component is described. An isometric figure and the pilot plant lay-out are included. The pilot plant occupying 41 m 2 has been tested and operates at its nominal capacity. (author) [pt

  19. Plant Research

    Science.gov (United States)

    1990-01-01

    The Land's agricultural research team is testing new ways to sustain life in space as a research participant with Kennedy Space Center's Controlled Ecological Life Support System (CELSS). The Land, sponsored by Kraft General Foods, is an entertainment, research, and education facility at EPCOT Center, part of Walt Disney World. The cooperative effort is simultaneously a research and development program, a technology demonstration that provides the public to see high technology at work and an area of potential spinoff: the CELSS work may generate Earth use technology beneficial to the hydroponic (soilless growing) vegetable production industries of the world.

  20. Fusion pilot plant scoping study

    International Nuclear Information System (INIS)

    Gierszewski, P.J.; Blevins, P.J.; Brunnader, H.; Natalizio, A.; Cumyn, P.; Dean, B.; Smith, S.; Galambos, J.; Holloway, C.; Stremlaw, J.; Williams, G.

    1994-05-01

    CFFTP Pilot is representative of a class of machines that, like NPD in the CANDU development program, could test the key reactor core technologies on an integrated power reactor relevant system (materials, conditions, configuration). But in order to reduce costs, the machine would operate at reduced neutron flux relative to a power reactor, would not produce electricity, and would not test superconducting magnets. This design shows research directions towards a machine that could provide integrated nuclear testing (but not ignition physics) at a cost of about 1/3 ITER CDA. The test volume - the outboard blanket volume - would be comparable to the test port volume on ITER CDA, while the fluence and power density would be about 1/4 ITER CDA. 91 refs., 43 tabs., 45 figs

  1. Fusion pilot plant scoping study

    Energy Technology Data Exchange (ETDEWEB)

    Gierszewski, P J; Blevins, P J; Brunnader, H; Natalizio, A [Canadian Fusion Fuels Technology Project, Toronto, ON (Canada); Cumyn, P [Canatom Ltd., Montreal, PQ (Canada); Dean, B; Smith, S [Wardrop (W.L.) and Associates Ltd., Winnipeg, MB (Canada); Galambos, J [Oak Ridge National Lab., TN (United States); Holloway, C [Spar Aerospace Ltd., Toronto, ON (Canada); Stremlaw, J [Monenco AGRA Inc., Calgary, AB (Canada); Williams, G [Spectrum Engineering Corp., Peterborough, ON (Canada)

    1994-05-01

    CFFTP Pilot is representative of a class of machines that, like NPD in the CANDU development program, could test the key reactor core technologies on an integrated power reactor relevant system (materials, conditions, configuration). But in order to reduce costs, the machine would operate at reduced neutron flux relative to a power reactor, would not produce electricity, and would not test superconducting magnets. This design shows research directions towards a machine that could provide integrated nuclear testing (but not ignition physics) at a cost of about 1/3 ITER CDA. The test volume - the outboard blanket volume - would be comparable to the test port volume on ITER CDA, while the fluence and power density would be about 1/4 ITER CDA. 91 refs., 43 tabs., 45 figs.

  2. Design of a uranium recovery pilot plant

    International Nuclear Information System (INIS)

    1984-01-01

    The engineering design of a pilot plant of uranium recover, is presented. The diagrams and specifications of the equipments such as pipelines, pumps, values tanks, filters, engines, etc... as well as metallic structure and architetonic design is also presented. (author)

  3. Achievement report for fiscal 1993 on developing entrained bed coal gasification power plant. Part 2. Summary of tests and researches on pilot plant operation; 1993 nendo seika hokokusho. Funryusho sekitan gaska hatsuden plant kaihatsu - Sono 2. Pilot plant unten shiken kenkyu no gaiyo hen

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-02-01

    Tests and researches have been carried out on operation of a 200-t/d entrained bed coal gasification pilot plant built with an objective of establishing the coal gasification composite power generation technology. This paper summarizes the achievements in fiscal 1993. The current fiscal year has performed the test operation on the pilot plant as a whole by using the coal D in continuation from the previous fiscal year. For the gasification furnace facilities, an air variation test was conducted for charging coal into the gasification furnace by using recovered oxygen, wherein satisfactory control was verified on oxygen concentration in the air supplied into the gasification furnace. In the gas refining facilities (dry desulfurizing facilities), the total sulfur concentration at 300 to 650 ppm in the gas produced from the coal gasification furnace was refined to 30 to 100 ppm, having achieved the initial target value. The gas refining facilities (dry dust collecting facilities) have achieved satisfactory result that the entrance dust concentration at 66 to 270 mg/Nm{sup 3} was reduced to the exit dust concentration at 1 to 3 mg/Nm{sup 3}. With respect to the gas turbine facilities, the planned values of output and thermal efficiency were satisfied, having derived good performance characteristics. (NEDO)

  4. Research of fluidized bed cement clinker sintering system by pilot plant; Ryudosho cement shosei gijutsu no kaihatsu. 7

    Energy Technology Data Exchange (ETDEWEB)

    Sugiyama, T [Center for Coal Utilization, Japan, Tokyo (Japan); Sato, N; Hashimoto, I; Nakatsuka, M [The Cement Association of Japan, Tokyo (Japan)

    1996-09-01

    While a cement manufacturing process generally performs sintering by using a rotary kiln, a development work has been carried out as a subsidy operation of the Agency of Natural Resources and Energy on a cement sintering technology using a fluidized bed consisted of two furnaces: a jet flow bed granulating furnace and a fluidized bed sintering furnace. This paper reports the results of tests and researches performed during fiscal 1995. A plant with a scale of 20 ton-a-day production started in 1993 after having gone through bench scale tests. The year 1995 conducted by August its performance evaluation, review of the operation method and the safety criteria, and generalization of the tests. A multi-stage cyclone system has been employed in the preheating equipment for cement material powder. A number of improvements have been realized in the aspects of construction and operation, such as stabilization of dust collecting efficiency by employing a high-efficiency type cyclone, and operation with reduced pressure variation. Based on these results, a construction had been progressed in parallel on a new plant upscaled to 200 ton-a-day production. The new plant was completed in December, 1995. 9 figs., 8 tabs.

  5. Pilot plant for exploitation of geothermal waters

    Directory of Open Access Journals (Sweden)

    Stojiljković Dragan T.

    2006-01-01

    Full Text Available In Sijarinska spa, there are some 15 mineral and thermomineral springs, that are already being used for therapeutic purposes. For the exploitation of heat energy boring B-4 is very interesting. It is a boring of a closed type, with the water temperature of about 78°C and a flow rate of about 33 l/s. Waters with the flow rate of about 6 l/s are currently used for heating of the Gejzer hotel, and waters of the flow rate of about 0,121 l/s for the pilot drying plant. The paper presents this pilot plant. .

  6. Achievement report for fiscal 1982 on Sunshine Program. Research and development of coal liquefaction technology (Conceptual designs for coal liquefaction pilot plants - Solvent extraction liquefaction process); 1982 nendo sekitan ekika gijutsu no kenkyu kaihatsu seika hokokusho. Sekitan ekika pilot plant no gainen sekkei (yozai chushutsu ekikaho)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1983-03-01

    This research aims to prepare conceptual designs for a 250t/d-class and 500t/d-class coal liquefaction pilot plants based on the achievement of research on solvent extraction liquefaction of coal. It also aims to define the solvent extraction process and provide decision-making material relative to the development and promotion of coal liquefaction technologies in the future. Development started in 1978 of the technology of solvent extraction liquefaction of coal, and a 1t/d PDU (process development unit) was completed in 1981. Studies through its operation have continued for more than 3000 hours already, and technical data are being accumulated steadily. Techniques acquired through operating the 1t/d PDU have been put together, and rough process conditions are established. A rough process result is achieved of the same conditions. In these two respects, the newly developed process is equal to other processes. The phenomena in this process are roughly grasped. It is deemed that, with the existing technique combined with the technique acquired here, a technological level has been reached where conceptual designs of large pilot plants may be worked out for solvent extraction liquefaction of coal. Under the circumstances, with a view to developing a commercial plant whose main products will be fuel oils, conceptual designs are prepared for large pilot plants, and are compiled into this report. (NEDO)

  7. 7 CFR 1412.48 - Planting Transferability Pilot Project.

    Science.gov (United States)

    2010-01-01

    ... 7 Agriculture 10 2010-01-01 2010-01-01 false Planting Transferability Pilot Project. 1412.48... and Peanuts 2008 through 2012 § 1412.48 Planting Transferability Pilot Project. (a) Notwithstanding § 1412.47, for each of the 2009 and subsequent crop years, the Planting Transferability Pilot Project...

  8. Waste Isolation Pilot Plant safety analysis report

    International Nuclear Information System (INIS)

    1997-03-01

    The United States Department of Energy (DOE) was authorized by Public Law 96-164 to provide a research and development facility for demonstrating the safe permanent disposal of transuranic (TRU) wastes from national defense activities and programs of the United States exempted from regulations by the US Nuclear Regulatory Commission (NRC). The Waste Isolation Pilot Plant (WIPP), located in southeastern New Mexico near Carlsbad, was constructed to determine the efficacy of an underground repository for disposal of TRU wastes. In accordance with the 1981 and 1990 Records of Decision (ROD), the development of the WIPP was to proceed with a phased approach. Development of the WIPP began with a siting phase, during which several sites were evaluated and the present site selected based on extensive geotechnical research, supplemented by testing. The site and preliminary design validation phase (SPDV) followed the siting phase, during which two shafts were constructed, an underground testing area was excavated, and various geologic, hydrologic, and other geotechnical features were investigated. The construction phase followed the SPDV phase during which surface structures for receiving waste were built and underground excavations were completed for waste emplacement

  9. Waste Isolation Pilot Plant borehole data

    International Nuclear Information System (INIS)

    1995-04-01

    Data pertaining to all the surface boreholes used at the WIPP site for site characterization hydrological testing and resource evaluation exist in numerous source documents. This project was initiated to develop a comprehensive data base that would include the data on all WIPP related surface boreholes from the Atomic Energy Commission, Waste Isolation Pilot Plant Energy Research and Development Administration, Department of Energy, and Hydrologic Test Borehole Programs. The data compiled from each borehole includes: operator, permit number, location, total depth, type of well, driller, drilling record, casing record, plugging schedule, and stratigraphic summary. There are six groups of boreholes contained in this data base, they are as follows: Commercially Drilled Potash Boreholes, Energy Department Wells, Geologic Exploration Boreholes, Hydrologic Test Boreholes, Potash Boreholes, and Subsurface Exploration Boreholes. There were numerous references which contained borehole data. In some cases the data found in one document was inconsistent with data in another document. In order to ensure consistency and accuracy in the data base, the same references were used for as many of the boreholes as possible. For example, all elevations and locations were taken from Compilation and Comparison of Test-Hole Location Surveys in the Vicinity of the WIPP Site. SAND 88-1065, Table 3-5. There are some sections where a data field is left blank. In this case, the information was either not applicable or was unavailable

  10. Waste Isolation Pilot Plant borehole data

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-04-01

    Data pertaining to all the surface boreholes used at the WIPP site for site characterization hydrological testing and resource evaluation exist in numerous source documents. This project was initiated to develop a comprehensive data base that would include the data on all WIPP related surface boreholes from the Atomic Energy Commission, Waste Isolation Pilot Plant Energy Research and Development Administration, Department of Energy, and Hydrologic Test Borehole Programs. The data compiled from each borehole includes: operator, permit number, location, total depth, type of well, driller, drilling record, casing record, plugging schedule, and stratigraphic summary. There are six groups of boreholes contained in this data base, they are as follows: Commercially Drilled Potash Boreholes, Energy Department Wells, Geologic Exploration Boreholes, Hydrologic Test Boreholes, Potash Boreholes, and Subsurface Exploration Boreholes. There were numerous references which contained borehole data. In some cases the data found in one document was inconsistent with data in another document. In order to ensure consistency and accuracy in the data base, the same references were used for as many of the boreholes as possible. For example, all elevations and locations were taken from Compilation and Comparison of Test-Hole Location Surveys in the Vicinity of the WIPP Site. SAND 88-1065, Table 3-5. There are some sections where a data field is left blank. In this case, the information was either not applicable or was unavailable.

  11. Ion exchange/adsorbent pilot plant

    International Nuclear Information System (INIS)

    Anon.

    1982-01-01

    A decontamination of greater than 99% of the actinides and fission products contained in radioactive waste water can be obtained using ion exchange resins. A system for achieving this result is described in this paper. This ion exchange pilot-plant design is the culmination of five years of study of the decontamination of radioactive waste streams by ion exchange resins and other adsorbents at Mound. In order to maintain maximum flexibility of treatments, this pilot-plant design is a conceptual design with specific flows, resins, and column specifications, but with many optional features and no rigid equipment specifications. This flexibility allows the system to be amenable to almost any radioactive waste stream. Very specific designs can be constructed from this conceptual design for the treatment of any specific waste stream. Operating and capital costs are also discussed. 1 figure, 5 tables

  12. Radioactive-waste isolation pilot plant

    International Nuclear Information System (INIS)

    Weart, W.D.

    1977-01-01

    The objective of the Waste Isolation Pilot Plant (WIPP) program is to demonstrate the suitability of bedded salt, specifically, the bedded salt deposits in the Los Medanos area of southeastern New Mexico, as a disposal medium for radioactive wastes. Our program responsibilities include site selection considerations, all aspects of design and development, technical guidance of facility operation, environmental impact assessment, and technical support to ERDA for developing public understanding of the facility

  13. Plant Research '75

    Energy Technology Data Exchange (ETDEWEB)

    1975-01-01

    Research is reported on stomatal regulation of the gas exchanges between plant and environment; inhibitory effects in flower formation; plant growth and development through hormones; hormone action; development and nitrogen fixation in algae; primary cell wall glycoprotein ectensin; enzymic mechanisms and control of polysaccharide and glycoprotein synthesis; molecular studies of membrane studies; sensory transduction in plants; regulation of formation of protein complexes and enzymes in higher plant cell and mechanism of sulfur dioxide toxicity in plants. (PCS)

  14. Pressurized fluidized bed combustion combined cycle power plant with coal gasification: Second generation pilot plant

    International Nuclear Information System (INIS)

    Farina, G.L.; Bressan, L.

    1991-01-01

    This paper presents the technical and economical background of a research and development program of a novel power generation scheme, which is based on coal gasification, pressurized fluid bed combustion and combined cycles. The participants in this program are: Foster Wheeler (project leader), Westinghouse, IGT and the USA Dept. of Energy. The paper describes the characteristics of the plant, the research program in course of implementation, the components of the pilot plant and the first results obtained

  15. The pilot plant for electron beam food processing

    International Nuclear Information System (INIS)

    Migdal, W.; Kosmal, W.; Malec-Czechowska, K.; Maciszewski, W.

    1992-01-01

    In the frames of the national programme on the application of irradiation for food preservation and hygienization an experimental plant for electron beam processing has been established in INCT. The pilot plant has been constructed inside an old fort what decreases significantly the cost of the investment. The pilot plants is equipped with a small research accelerator Pilot (10 MeV, 1 kW) and an industrial unit Elektronika (10 MeV, 10 kW). This allows both laboratory and full technological scale testing of the elaborated process to be conducted. The industrial unit is being equipped with e-/X conversion target, for high density products irradiation. On the basis of the research there were performed at different scientific institutions in Poland, health authorities have issued permissions for permanent treatment of spices, garlic, onions and temporary permissions for mushrooms, and potatoes. Dosimetric methods have been elaborated for the routine use at the plant. In the INCT laboratory methods for the control of e-/X treated food have been established. (author). 9 refs, 5 figs, 1 tab

  16. The pilot plant for electron beam food processing

    Science.gov (United States)

    Migdal, W.; Walis, L.; Chmielewski, A. G.

    1993-07-01

    In the frames of the national programme on the application of irradiation for food preservation and hygienization an experimental plant for electron beam processing has been established in INCT. The pilot plant has been constructed inside an old fort what decreases significantly the cost of the investment. The pilot plant is equipped with a small research accelerator Pilot (10 MeV, 1 kW) and an industrial unit Elektronika (10 MeV, 10 kW). This allows both laboratory and full technological scale testing of the elaborated process to be conducted. The industrial unit is being equipped with e-/X conversion target, for high density products irradiation. On the basis of the research there were performed at different scientific institutions in Poland, health authorities have issued permissions for permanent treatment of spices, garlic, onions and temporary permissions for mushrooms, and potatoes. Dosimetric methods have been elaborated for the routine use at the plant. In the INCT laboratory methods for the control of e-/X treated food have been established.

  17. Plan for the civil reprocessing pilot plant of China

    International Nuclear Information System (INIS)

    Wang, D.Y.; Chen, M.

    1987-01-01

    Based on the R and D work, experience on plant operation and site situation, the necessity and feasibility of building a pilot plant for civil reprocessing in China are discussed. The capacity of 100 kg HM/day (LWR) and 3 kg HM/day (MTR) has been proposed. The plant consists of cold testing facility and hot pilot facility. It is expected to complete the pilot plant in 1990's. This paper also describes the purpose, scale, process and equipment of the pilot plant

  18. A review on pilot plant development models

    International Nuclear Information System (INIS)

    Rosli Darmawan

    2005-01-01

    After more than 30 years, MINT has been able to produce many new findings, products and processes. Some of these have been able to penetrate local and international markets. This was achieved through a systematic commercialisation program practiced in MINT with its technological chain and MINT Technology Park program. This paper will review the development process of MINT pilot plants and compare them with a few other models from other institutions in Malaysia and abroad. The advantages and disadvantages of each model are reviewed and a discussion against MINT's model is presented. (Author)

  19. Vitrification pilot plant experiences at Fernald, Ohio

    International Nuclear Information System (INIS)

    Akgunduz, N.; Gimpel, R.F.; Paine, D.; Pierce, V.H.

    1997-01-01

    A one metric ton/day Vitrification Pilot Plant (VITPP) at Fernald, Ohio, simulated the vitrification of radium and radon bearing silo residues using representative non-radioactive surrogates containing high concentrations of lead, sulfates, and phosphates. The vitrification process was carried out at temperatures of 1,150 to 1,350 C. The VITPP processed glass for seven months, until a breach of the melter containment vessel suspended operations. More than 70,000 pounds of surrogate glass were produced by the VITPP. Experiences, lessons learned, and path forward will be presented

  20. Pilot plant experiments at Wairakei Power Station

    International Nuclear Information System (INIS)

    Brown, Kevin L.; Bacon, Lew G.

    2009-01-01

    In the mid-1990s, several pilot plants were constructed at Wairakei to either improve the operational and economic performance of the power station or to mitigate the environmental effects of discharges to the Waikato River. The results of the following investigations are discussed: (1) fluid flow dynamic effects on silica scaling; (2) production of silica sols of predetermined particle size to evaluate the potential for generating commercial grade silica products; (3) use of 'sulfur oxidising bacteria' for the abatement of dissolved hydrogen sulphide in cooling water; (4) removal of arsenic from separated geothermal water; (5) steam line condensate corrosion; and (6) measurement and modelling of steam scrubbing in Wairakei's long steamlines. (author)

  1. Italian experience with pilot reprocessing plants

    International Nuclear Information System (INIS)

    Cao, S.; Dworschak, H.; Rolandi, G.; Simonetta, R.

    1977-01-01

    Problems and difficulties recently experienced in the reprocessing technology of high burnup power reactor fuel elements have shown the importance of pilot plant experiments to optimize the separation processes and to test advanced equipment on a representative scale. The CNEN Eurex plant, in Saluggia (Vercelli), with a 50 kg/d thruput, in operation since '71, has completed several reprocessing campaigns on MTR type fuel elements. Two different chemical flowsheets based respectively on TBP and tertiary amines were thoroughly tested and compared: a concise comparative evaluation of the results obtained with the two schemes is given. Extensive modifications have then been introduced (namely a new headend cell equipped with a shear) to make the plant suitable to reprocess power reactor fuels. The experimental program of the plant includes a joint CNEN-AECL reprocessing experiment on CANDU (Pickering) type fuel elements to demonstrate a two cycle, amine based recovery of the plutonium. Later, a stock of high burnup fuel elements from the PWR Trino power station will be reprocessed to recover Pu and U with a Purex type flowsheet. ITREC, the second CNEN experimental reprocessing plant located at Trisaia Nuclear Center (Matera), started active operation two years ago. In the first campaign Th-U mixed oxide fuel elements irradiated in the Elk River reactor were processed. Results of this experiment are reported. ITREC special design features confer a high degree of versability to the plant allowing for substantial equipment modification under remote control conditions. For this reason the plant will be principally devoted in the near future to advanced equipment testing. Along this line high speed centrifugal contactor of a new type developed in Poland will be tested in the plant in the frame of a joint experiment between CNEN and the Polish AEC. Later on the plant program will include experimental campaign on fast reactor fuels; a detailed study on this program is in

  2. Pilot plant of continuous ion-exchange in fluidized bed

    International Nuclear Information System (INIS)

    Botella, T.; Otero de Becerra, J.; Gasos, P.

    1985-01-01

    Research and development on continuous ion-exchange processes has been a major item in hydrometallurgy. This new technology has been under development during the last 15 years in the leading countries at uranium hydrometallurgy. The fluidized bed multi-stage column technique is proven to be the most attractive one, and since 1977 several commercial plants have begun production, some of them with a throughput of 500 cubic meters of pregnant liquour per hour. J.E.N. undertook the study of this new technology for uranium recovery in the early 70's. In 1979 a pilot plant had been installed, based on previous laboratory and smaller pilot plant experience. The plant was designed following JEN's own technology and has been operating successfully at a flow rate of near 0.5 cubic meters per hour. The test runs and the main processing, engineering and operation features are described. At present a demonstation plant is under design, and this installation will provide the necessary know-how for the construction and operation of a commercial scale plant. (author)

  3. DU-AGG pilot plant design study

    International Nuclear Information System (INIS)

    Lessing, P.A.; Gillman, H.

    1996-07-01

    The Idaho National Engineering Laboratory (INEL) is developing new methods to produce high-density aggregate (artificial rock) primarily consisting of depleted uranium oxide. The objective is to develop a low-cost method whereby uranium oxide powder (UO[sub 2], U[sub 3]O[sub ]8, or UO[sub 3]) can be processed to produce high-density aggregate pieces (DU-AGG) having physical properties suitable for disposal in low-level radioactive disposal facilities or for use as a component of high-density concrete used as shielding for radioactive materials. A commercial company, G-M Systems, conducted a design study for a manufacturing pilot plant to process DU-AGG. The results of that study are included and summarized in this report. Also explained are design considerations, equipment capacities, the equipment list, system operation, layout of equipment in the plant, cost estimates, and the proposed plan and schedule

  4. Photovoltaic pilot plant of Vulcano (Italy)

    Energy Technology Data Exchange (ETDEWEB)

    Menga, P.; Previ, A.

    1988-12-31

    The rated peak power of the Vulcano plant is about 80 kW. The main feature of the plant lies in its dual operating mode: either stand-alone or grid-connected. The plant, commissioned half-way through 1984, has always worked uninterruptedly and satisfactorily and, for this reason, it is expected to keep on operating in the coming years. Beginning from 1987, it has been considered worth carrying out research on a number of specific points not so far dealt with in sufficient detail in literature, as follows: experimental research on the deterioration, over a period of time, of the characteristics of the modules of the plant; theoretical and experimental research on the plant`s electrochemical storage system. The research on the second of the above subjects has a number of aims: to improve methods of checking the state of charge of batteries in newly-designed photovoltaic plants; to improve the ways in which the Vulcano battery storage system is operated; and to monitor and make a careful diagnosis of the condition of the plant`s battery.

  5. Waste Isolation Pilot Plant, Land Management Plan

    Energy Technology Data Exchange (ETDEWEB)

    1993-12-01

    To reflect the requirement of section 4 of the Wastes Isolation Pilot Plant Land Withdrawal Act (the Act) (Public Law 102-579), this land management plan has been written for the withdrawal area consistent with the Federal Land Policy and Management Act of 1976. The objective of this document, per the Act, is to describe the plan for the use of the withdrawn land until the end of the decommissioning phase. The plan identifies resource values within the withdrawal area and promotes the concept of multiple-use management. The plan also provides opportunity for participation in the land use planning process by the public and local, State, and Federal agencies. Chapter 1, Introduction, provides the reader with the purpose of this land management plan as well as an overview of the Waste Isolation Pilot Plant. Chapter 2, Affected Environment, is a brief description of the existing resources within the withdrawal area. Chapter 3, Management Objectives and Planned Actions, describes the land management objectives and actions taken to accomplish these objectives.

  6. Waste Isolation Pilot Plant, Land Management Plan

    International Nuclear Information System (INIS)

    1993-01-01

    To reflect the requirement of section 4 of the Wastes Isolation Pilot Plant Land Withdrawal Act (the Act) (Public Law 102-579), this land management plan has been written for the withdrawal area consistent with the Federal Land Policy and Management Act of 1976. The objective of this document, per the Act, is to describe the plan for the use of the withdrawn land until the end of the decommissioning phase. The plan identifies resource values within the withdrawal area and promotes the concept of multiple-use management. The plan also provides opportunity for participation in the land use planning process by the public and local, State, and Federal agencies. Chapter 1, Introduction, provides the reader with the purpose of this land management plan as well as an overview of the Waste Isolation Pilot Plant. Chapter 2, Affected Environment, is a brief description of the existing resources within the withdrawal area. Chapter 3, Management Objectives and Planned Actions, describes the land management objectives and actions taken to accomplish these objectives

  7. Pilot plant for hydrogasification of coal with nuclear heat

    International Nuclear Information System (INIS)

    Falkenhain, G.; Velling, G.

    1976-01-01

    In the framework of a research and development programme sponsored by the Ministry of Research and Technology of the Federal Republic of Germany, two process variants for hydrogasification of coal by means of nuclear heat have been developed by the Rheinische Braunkohlenwerke AG, Cologne. For testing these process variants a semi-technical pilot plant for gasification of coal under pressure in a fluidized bed was constructed. The pilot plant, in which the gasification of lignite and hard coal is planned, is designed for a throughput of 100kg carbon per hour corresponding to 400kg raw lignite per hour or 150kg hard coal per hour. The plant should provide data on the influence of the most essential process parameters (pressure, temperature, residence time of gas and coal, type and pre-treatment of feed coal) on the performance of gasification and raw gas composition. Different plant components will also be tested. Since the pilot plant will permit testing of both process variants of hydrogasification, it was designed in such a way that it is possible to vary a great number of process parameters. Thus, for instance, the pressure can be chosen in a range up to 100 bar and pure hydrogen or mixtures of hydrogen, carbon monoxide and steam can be applied as gasification agents. The gasifier is an internally insulated fluidized bed reactor with an inner diameter of 200mm and a height of about 8m, to which an internally insulated cyclone for separation of the entrained fines is attached. The raw gas is then cooled down by direct water scrubbing. (author)

  8. TASK 3: PILOT PLANT GASIFIER TESTING

    Energy Technology Data Exchange (ETDEWEB)

    Fusselman, Steve

    2015-11-01

    Aerojet Rocketdyne (AR) has developed an innovative gasifier concept incorporating advanced technologies in ultra-dense phase dry feed system, rapid mix injector, and advanced component cooling to significantly improve gasifier performance, life, and cost compared to commercially available state-of-the-art systems. Design, fabrication and initial testing of the pilot plant compact gasifier was completed in 2011 by a development team led by AR. Findings from this initial test program, as well as subsequent gasifier design and pilot plant testing by AR, identified a number of technical aspects to address prior to advancing into a demonstration-scale gasifier design. Key among these were an evaluation of gasifier ability to handle thermal environments with highly reactive coals; ability to handle high ash content, high ash fusion temperature coals with reliable slag discharge; and to develop an understanding of residual properties pertaining to gasification kinetics as carbon conversion approaches 99%. The gasifier did demonstrate the ability to withstand the thermal environments of highly reactive Powder River Basin coal, while achieving high carbon conversion in < 0.15 seconds residence time. Continuous operation with the high ash fusion temperature Xinyuan coal was demonstrated in long duration testing, validating suitability of outlet design as well as downstream slag discharge systems. Surface area and porosity data were obtained for the Xinyuan and Xinjing coals for carbon conversion ranging from 85% to 97%, and showed a pronounced downward trend in surface area per unit mass carbon as conversion increased. Injector faceplate measurements showed no incremental loss of material over the course of these experiments, validating the commercially traceable design approach and supportive of long injector life goals. Hybrid testing of PRB and natural gas was successfully completed over a wide range of natural gas feed content, providing test data to anchor predictions

  9. FY 1996 report on the cooperative research on the development of environmentally friendly high efficiency mineral resource extraction/treatment technology. Basic design of pilot plant and a part of the detailed design; 1996 nendo kankyo chowagata kokoritsu kobutsu shigen chushutsu shori gijutsu no kaihatsu ni kansuru kenkyu kyoryoku. Pilot plant no kihon sekkei oyobi ichibu shosai sekkei

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-03-01

    This project is a cooperative research on the development of environmental harmony type high efficiency mineral resource extraction/treatment technology. It aims to study/develop a system to recover valuable metals from unused resources in the Republic of Kazakhstan using the environmental harmony type technology which is easy to operate/maintain and is environmentally friendly with no mine pollution caused. In the project, which started in FY 1994, a pilot plant is finally constructed in Kazakhstan, a recovery system to be applied is demonstrated, and the comprehensive assessment of the system is made. Concretely, the recovery of Cu, Au, Ag, etc. is tried from the Nikolayevska low grade ore and Zhezkent tailings. This is a system into which the following techniques are integrated: treatment before dressing such as flotation, leaching of Cu, etc. by acid including bacteria, solvent leaching, electrowinning, cyanogen leaching activated carbon treatment and wastewater treatment of Au and Ag. As to the design/fabrication of pilot plant, conducted was the conceptual design in FY 1995, and the basic design, a part of the detailed design (crushing/grinding/leaching/dewatering facilities of the process of the acid (bacteria) leaching of Cu, etc.), and the fabrication in FY 1996. (NEDO).

  10. Pilot and pilot-commercial plants for reprocessing spent fuels of FBR type reactors

    International Nuclear Information System (INIS)

    Shaldaev, V.S.; Sokolova, I.D.

    1988-01-01

    A review of modern state of investigations on the FBR mixed oxide uranium-plutonium fuel reprocessing abroad is given. Great Britain and France occupy the leading place in this field, operating pilot plants of 5 tons a year capacity. Technology of spent fuel reprocessing and specific features of certain stages of the technological process are considered. Projects of pilot and pilot-commercial plants of Great Britain, France, Japan, USA are described. Economic problems of the FBR fuel reprocessing are touched upon

  11. Waste Isolation Pilot Plant Safety Analysis Report

    International Nuclear Information System (INIS)

    1995-11-01

    The following provides a summary of the specific issues addressed in this FY-95 Annual Update as they relate to the CH TRU safety bases: Executive Summary; Site Characteristics; Principal Design and Safety Criteria; Facility Design and Operation; Hazards and Accident Analysis; Derivation of Technical Safety Requirements; Radiological and Hazardous Material Protection; Institutional Programs; Quality Assurance; and Decontamination and Decommissioning. The System Design Descriptions'' (SDDS) for the WIPP were reviewed and incorporated into Chapter 3, Principal Design and Safety Criteria and Chapter 4, Facility Design and Operation. This provides the most currently available final engineering design information on waste emplacement operations throughout the disposal phase up to the point of permanent closure. Also, the criteria which define the TRU waste to be accepted for disposal at the WIPP facility were summarized in Chapter 3 based on the WAC for the Waste Isolation Pilot Plant.'' This Safety Analysis Report (SAR) documents the safety analyses that develop and evaluate the adequacy of the Waste Isolation Pilot Plant Contact-Handled Transuranic Wastes (WIPP CH TRU) safety bases necessary to ensure the safety of workers, the public and the environment from the hazards posed by WIPP waste handling and emplacement operations during the disposal phase and hazards associated with the decommissioning and decontamination phase. The analyses of the hazards associated with the long-term (10,000 year) disposal of TRU and TRU mixed waste, and demonstration of compliance with the requirements of 40 CFR 191, Subpart B and 40 CFR 268.6 will be addressed in detail in the WIPP Final Certification Application scheduled for submittal in October 1996 (40 CFR 191) and the No-Migration Variance Petition (40 CFR 268.6) scheduled for submittal in June 1996. Section 5.4, Long-Term Waste Isolation Assessment summarizes the current status of the assessment

  12. Waste Isolation Pilot Plant Safety Analysis Report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-11-01

    The following provides a summary of the specific issues addressed in this FY-95 Annual Update as they relate to the CH TRU safety bases: Executive Summary; Site Characteristics; Principal Design and Safety Criteria; Facility Design and Operation; Hazards and Accident Analysis; Derivation of Technical Safety Requirements; Radiological and Hazardous Material Protection; Institutional Programs; Quality Assurance; and Decontamination and Decommissioning. The System Design Descriptions`` (SDDS) for the WIPP were reviewed and incorporated into Chapter 3, Principal Design and Safety Criteria and Chapter 4, Facility Design and Operation. This provides the most currently available final engineering design information on waste emplacement operations throughout the disposal phase up to the point of permanent closure. Also, the criteria which define the TRU waste to be accepted for disposal at the WIPP facility were summarized in Chapter 3 based on the WAC for the Waste Isolation Pilot Plant.`` This Safety Analysis Report (SAR) documents the safety analyses that develop and evaluate the adequacy of the Waste Isolation Pilot Plant Contact-Handled Transuranic Wastes (WIPP CH TRU) safety bases necessary to ensure the safety of workers, the public and the environment from the hazards posed by WIPP waste handling and emplacement operations during the disposal phase and hazards associated with the decommissioning and decontamination phase. The analyses of the hazards associated with the long-term (10,000 year) disposal of TRU and TRU mixed waste, and demonstration of compliance with the requirements of 40 CFR 191, Subpart B and 40 CFR 268.6 will be addressed in detail in the WIPP Final Certification Application scheduled for submittal in October 1996 (40 CFR 191) and the No-Migration Variance Petition (40 CFR 268.6) scheduled for submittal in June 1996. Section 5.4, Long-Term Waste Isolation Assessment summarizes the current status of the assessment.

  13. Ningyo Toge uranium enrichment pilot plant comes into full

    International Nuclear Information System (INIS)

    1982-01-01

    The uranium enrichment pilot plant of the Power Reactor and Nuclear Fuel Development Corporation at Ningyo Toge went into full operation on March 26, 1982. This signifies that the front end of the nuclear fuel cycle in Japan, from uranium ore to enrichment, is only a step away from commercialization. On the same day, the pilot plant of uranium processing and conversion to UF 6 , the direct purification of uranium ore into uranium hexafluoride, began batch operation at the same works. The construction of the uranium enrichment pilot plant has been advanced in three stages: i.e. OP-1A with 1000 centrifuges, OP-1B with 3000 centrifuges and OP-2 with 3000 centrifuges. With a total of 7000 centrifuges, the pilot plant, the first enrichment plant in Japan, has now a capacity of supplying enriched uranium for six months operation of a 1,000 MW nuclear power plant. (J.P.N.)

  14. The Waste Isolation Pilot Plant status and related socioeconomic impacts

    International Nuclear Information System (INIS)

    Little, C.C.; Adcock, L.D.; Hohmann, G.L.

    1984-01-01

    The Waste Isolation Pilot Plant (WIPP) has been ''authorized as a defense activity of the Department of Energy...for the express purpose of providing a research and development facility to demonstrate the safe disposal of radioactive wastes resulting from the defense activities and programs of the United States...'' (PL 96-164). As reported in previous conferences, WIPP continues ahead of schedule and below budget with full facility construction well underway. To date, based on recent review, the socioeconomic impacts have been negligible and steps have been taken to ensure that they remain that way throughout operations

  15. Pilot plant study for ethanol production

    Energy Technology Data Exchange (ETDEWEB)

    Kim, J S [Korea Inst. of Science and Technology, Seoul (Korea, Republic of)

    1996-02-01

    Most of domestic alcohol fermentation factory adopt batch process of which productivity is lower than continuous fermentation process. They have made great effort to increase productivity by means of partial unit process automatization and process improvement with their accumulated experience but there is technical limitation in productivity of batch fermentation process. To produce and supply fuel alcohol, economic aspects must be considered first of all. Therefore, development of continuous fermentation process, of which productivity is high, is prerequisite to produce and use fuel alcohol but only a few foreign company possess continuous fermentation technic and use it in practical industrial scale fermentation. We constructed pilot plant (5 Stage CSTR 1 kl 99.5 v/v% ethanol/Day scale) to study some aspects stated below and our ultimate aims are production of industrial scale fuel alcohol and construction of the plant by ourselves. Some study concerned with energy saving separation and contamination control technic were entrusted to KAIST, A-ju university and KIST respectively. (author) 67 refs., 100 figs., 58 tabs.

  16. Reports on 1977 result of research. Investigation for selecting site location of pilot plant for 7,000Nm{sup 3}/day class high calorie gasification; 1977 nendo sunshine keikaku ni kakawaru plant kenkyu kaihatsu seika hokoku. 7,000Nm{sup 3}/nichi kyu kokarori gas ka pilot plant yochi no ricchi sentei chosa

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1978-03-20

    A report was made on the result of investigation for selecting a suitable site for a coal gasification pilot plant. The high calorie gasification plant under the Sunshine Project is scheduled to have a parallel operation of two methods. It could be decided on one only method depending on the future studies. One is the 'water gasification method' using coal only as the raw material, with hydrogen gas added to contrive methanization. The other is the 'hybrid gasification method' using mixed slurry of powdered coal and heavy oil as the raw material, with oxygen supplied to it to form a clean gas. The sites proposed for the pilot plant are the cities of Yubari, Iwaki, Kita-Ibaraki, Tagawa, Iizuka and Imari. The items for assessment of cost effectiveness are the expenses of development of a site, road construction, removal of existing obstacles, plant construction, power receiving equipment construction, irrigation supply facilities construction, wastewater treatment system construction, ash discharging system construction, transportation, and supply/processing-related maintenance. As a result of the assessment, Iwaki city was picked up as the area almost free from drawbacks to cost effectiveness. (NEDO)

  17. Reports on 1977 result of research. Investigation for selecting site location of pilot plant for 7,000Nm{sup 3}/day class high calorie gasification; 1977 nendo sunshine keikaku ni kakawaru plant kenkyu kaihatsu seika hokoku. 7,000Nm{sup 3}/nichi kyu kokarori gas ka pilot plant yochi no ricchi sentei chosa

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1978-03-20

    A report was made on the result of investigation for selecting a suitable site for a coal gasification pilot plant. The high calorie gasification plant under the Sunshine Project is scheduled to have a parallel operation of two methods. It could be decided on one only method depending on the future studies. One is the 'water gasification method' using coal only as the raw material, with hydrogen gas added to contrive methanization. The other is the 'hybrid gasification method' using mixed slurry of powdered coal and heavy oil as the raw material, with oxygen supplied to it to form a clean gas. The sites proposed for the pilot plant are the cities of Yubari, Iwaki, Kita-Ibaraki, Tagawa, Iizuka and Imari. The items for assessment of cost effectiveness are the expenses of development of a site, road construction, removal of existing obstacles, plant construction, power receiving equipment construction, irrigation supply facilities construction, wastewater treatment system construction, ash discharging system construction, transportation, and supply/processing-related maintenance. As a result of the assessment, Iwaki city was picked up as the area almost free from drawbacks to cost effectiveness. (NEDO)

  18. Study on designing a complete pilot plant for processing sandstone ores in Palua-Parong area

    International Nuclear Information System (INIS)

    Le Quang Thai; Tran Van Son; Tran The Dinh; Trinh Nguyen Quynh; Vu Khac Tuan

    2015-01-01

    Design work is the first step of the construction and operation of pilot plant. Thus, the project Study on designing a complete pilot plant for processing sandstone ores in Palua - Parong area was conducted to design a pilot plant for testing entire technological process to obtain yellowcake. Based on a literature review of uranium ore processing technology in the world, information of ore and previous research results of uranium ore in PaLua - PaRong area at the Institute for Technology of Radioactive and Rare Elements, a suitable technological flowsheet for processing this ore has been selected. The size, location of the pilot plant and planed experiments has been selected during the implementation of this project, in which basic parameters, designed system of equipment, buildings, ect. were also calculated. (author)

  19. Draft environmental assessment: Ocean Thermal Energy Conversion (OTEC) Pilot Plants

    Energy Technology Data Exchange (ETDEWEB)

    Sullivan, S.M.; Sands, M.D.; Donat, J.R.; Jepsen, P.; Smookler, M.; Villa, J.F.

    1981-02-01

    This Environmental Assessment (EA) has been prepared, in accordance with the National Environmental Policy Act of 1969, for the deployment and operation of a commercial 40-Megawatt (MW) Ocean Thermal Energy Conversion (OTEC) Pilot Plant (hereafter called the Pilot Plant). A description of the proposed action is presented, and a generic environment typical of the candidate Pilot Plant siting regions is described. An assessment of the potential environmental impacts associated with the proposed action is given, and the risk of credible accidents and mitigating measures to reduce these risks are considered. The Federal and State plans and policies the proposed action will encompass are described. Alternatives to the proposed action are presented. Appendix A presents the navigation and environmental information contained in the US Coast Pilot for each of the candidate sites; Appendix B provides a brief description of the methods and calculations used in the EA. It is concluded that environmental disturbances associated with Pilot Plant activities could potentially cause significant environmental impacts; however, the magnitude of these potential impacts cannot presently be assessed, due to insufficient engineering and environmental information. A site- and design-specific OTEC Pilot Plant Environmental Impact Statement (EIS) is required to resolve the potentially significant environmental effects associated with Pilot Plant deployment and operation. (WHK)

  20. Research of Brazilian crude in pilot plant for base oil production; Pesquisa em planta piloto visando valorizar o cru nacional na producao de oleos lubrificantes

    Energy Technology Data Exchange (ETDEWEB)

    Fontes, Anita E.F.; Nogueira, Wlamir S.; Ximenes, Lelia M. de O. [PETROBRAS, Rio de Janeiro, RJ (Brazil). Centro de Pesquisas (CENPES); Santos, Claudio A.P. dos [Fundacao Gorceix, Ouro Preto, MG (Brazil)

    2004-07-01

    One of the biggest challenges for PETROBRAS is to find alternative crude oils to produce base oil and wax in its refinery. Duque de Caxias refinery has been using imported crude oil for 31 years living with constants threats to continuity because of the Persian Gulf conflicts. If we analyze the profitability of this business, we can verify that the lubes complex had contributed for the profitability by about 41,9% in 2002, even using imported crude oil. So, if we can incorporate a national crude oil in the actual refinery scheme, we would produce besides strategic gains better profitability for the base oil and wax unit. This paper describes a series of tests performed in the pilot plant, in which we produced base oils and wax using a mixture of imported crude with Brazilian crude oil. The base oils produced were classified as Group I with lower aromatic, Sulphur and basic Nitrogen content. Another great advantage of this alternative is that the light fractions obtained from distillation step can be used as feed to make fuels of better quality, due to the lower sulphur content, thus also reducing the environmental impact. (author)

  1. Research Data Curation Pilots: Lessons Learned

    Directory of Open Access Journals (Sweden)

    David Minor

    2014-07-01

    Full Text Available In the spring of 2011, the UC San Diego Research Cyberinfrastructure (RCI Implementation Team invited researchers and research teams to participate in a research curation and data management pilot program. This invitation took the form of a campus-wide solicitation. More than two dozen applications were received and, after due deliberation, the RCI Oversight Committee selected five curation-intensive projects. These projects were chosen based on a number of criteria, including how they represented campus research, varieties of topics, researcher engagement, and the various services required. The pilot process began in September 2011, and will be completed in early 2014. Extensive lessons learned from the pilots are being compiled and are being used in the on-going design and implementation of the permanent Research Data Curation Program in the UC San Diego Library. In this paper, we present specific implementation details of these various services, as well as lessons learned. The program focused on many aspects of contemporary scholarship, including data creation and storage, description and metadata creation, citation and publication, and long term preservation and access. Based on the lessons learned in our processes, the Research Data Curation Program will provide a suite of services from which campus users can pick and choose, as necessary. The program will provide support for the data management requirements from national funding agencies.

  2. Waste Isolation Pilot Plant No-migration variance petition

    International Nuclear Information System (INIS)

    1990-03-01

    This report describes various aspects of the Waste Isolation Pilot Plant (WIPP) including design data, waste characterization, dissolution features, ground water hydrology, natural resources, monitoring, general geology, and the gas generation/test program

  3. Waste Isolation Pilot Plant Salt Decontamination Testing

    Energy Technology Data Exchange (ETDEWEB)

    Rick Demmer; Stephen Reese

    2014-09-01

    On February 14, 2014, americium and plutonium contamination was released in the Waste Isolation Pilot Plant (WIPP) salt caverns. At the request of WIPP’s operations contractor, Idaho National Laboratory (INL) personnel developed several methods of decontaminating WIPP salt, using surrogate contaminants and also americium (241Am). The effectiveness of the methods is evaluated qualitatively, and to the extent possible, quantitatively. One of the requirements of this effort was delivering initial results and recommendations within a few weeks. That requirement, in combination with the limited scope of the project, made in-depth analysis impractical in some instances. Of the methods tested (dry brushing, vacuum cleaning, water washing, strippable coatings, and mechanical grinding), the most practical seems to be water washing. Effectiveness is very high, and it is very easy and rapid to deploy. The amount of wastewater produced (2 L/m2) would be substantial and may not be easy to manage, but the method is the clear winner from a usability perspective. Removable surface contamination levels (smear results) from the strippable coating and water washing coupons found no residual removable contamination. Thus, whatever is left is likely adhered to (or trapped within) the salt. The other option that shows promise is the use of a fixative barrier. Bartlett Nuclear, Inc.’s Polymeric Barrier System (PBS) proved the most durable of the coatings tested. The coatings were not tested for contaminant entrapment, only for coating integrity and durability.

  4. Waste isolation pilot plant disposal room model

    Energy Technology Data Exchange (ETDEWEB)

    Butcher, B.M.

    1997-08-01

    This paper describes development of the conceptual and mathematical models for the part of the Waste Isolation Pilot Plant (WIPP) repository performance assessment that is concerned with what happens to the waste over long times after the repository is decommissioned. These models, collectively referred to as the {open_quotes}Disposal Room Model,{close_quotes} describe the repository closure process during which deformation of the surrounding salt consolidates the waste. First, the relationship of repository closure to demonstration of compliance with the Environmental Protection Agency (EPA) standard (40 CFR 191 Appendix C) and how sensitive performance results are to it are examined. Next, a detailed description is provided of the elements of the disposal region, and properties selected for the salt, waste, and other potential disposal features such as backfill. Included in the discussion is an explanation of how the various models were developed over time. Other aspects of closure analysis, such as the waste flow model and method of analysis, are also described. Finally, the closure predictions used in the final performance assessment analysis for the WIPP Compliance Certification Application are summarized.

  5. Waste Isolation Pilot Plant Strategic Plan

    International Nuclear Information System (INIS)

    1993-03-01

    The purpose of the Waste Isolation Pilot Plant (WIPP) Strategic Plan is to provide decision makers, project participants, and the public with a high-level overview of the objectives, issues, and strategiesthat impact a decision on the suitability of WIPP as a permanent, safe disposal facility for transuranic (TRU) waste that has resulted from defense activities. This document is a component of an integrated planning process and is a key management tool that is coordinated and consistent with the Secretary's Disposal Decision Plan and the Environmental Restoration and Waste Management (EM) Five-Year Plan. This documentsupports other US Department of Energy (DOE) planning efforts, including the TRU Waste Program. The WIPP Strategic Plan addresses the WIPP Program Test Phase, Disposal Decision, Disposal Phase, and Decommissioning Phase (decontamination and decommissioning). It describes the actions and activities that the DOE will conduct to ensure that WIPP will comply with applicable, relevant, and appropriate requirements of the US Environmental Protection Agency (EPA), State of New Mexico, and other applicable federal and state regulations. It also includes the key assumptions under which the strategy was developed. A comprehensive discussion of the multitude of activities involved in the WIPP Program cannot be adequately presented in this document. The specific details of these activities are presented in other, more detailed WIPP planningdocuments

  6. Waste isolation pilot plant disposal room model

    International Nuclear Information System (INIS)

    Butcher, B.M.

    1997-08-01

    This paper describes development of the conceptual and mathematical models for the part of the Waste Isolation Pilot Plant (WIPP) repository performance assessment that is concerned with what happens to the waste over long times after the repository is decommissioned. These models, collectively referred to as the open-quotes Disposal Room Model,close quotes describe the repository closure process during which deformation of the surrounding salt consolidates the waste. First, the relationship of repository closure to demonstration of compliance with the Environmental Protection Agency (EPA) standard (40 CFR 191 Appendix C) and how sensitive performance results are to it are examined. Next, a detailed description is provided of the elements of the disposal region, and properties selected for the salt, waste, and other potential disposal features such as backfill. Included in the discussion is an explanation of how the various models were developed over time. Other aspects of closure analysis, such as the waste flow model and method of analysis, are also described. Finally, the closure predictions used in the final performance assessment analysis for the WIPP Compliance Certification Application are summarized

  7. Waste Isolation Pilot Plant Environmental Monitoring Plan

    International Nuclear Information System (INIS)

    2008-01-01

    U.S. Department of Energy (DOE) Order 450.1, Environmental Protection Program, requires each DOE site to conduct environmental monitoring. Environmental monitoring at the Waste Isolation Pilot Plant (WIPP) is conducted in order to: (a) Verify and support compliance with applicable federal, state, and local environmental laws, regulations, permits, and orders; (b) Establish baselines and characterize trends in the physical, chemical, and biological condition of effluent and environmental media; (c) Identify potential environmental problems and evaluate the need for remedial actions or measures to mitigate the problems; (d) Detect, characterize, and report unplanned releases; (e) Evaluate the effectiveness of effluent treatment and control, and pollution abatement programs; and (f) Determine compliance with commitments made in environmental impact statements, environmental assessments, safety analysis reports, or other official DOE documents. This Environmental Monitoring Plan (EMP) explains the rationale and design criteria for the environmental monitoring program, extent and frequency of monitoring and measurements, procedures for laboratory analyses, quality assurance (QA) requirements, program implementation procedures, and direction for the preparation and disposition of reports. Changes to the environmental monitoring program may be necessary to allow the use of advanced technology and new data collection techniques. This EMP will document changes in the environmental monitoring program. Guidance for preparation of EMPs is contained in DOE/EH-0173T, Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance.

  8. Waste Isolation Pilot Plant (WIPP) startup plan

    International Nuclear Information System (INIS)

    1988-03-01

    To allow the Waste Isolation Pilot Plant (WIPP) to transition from a Major System Acquisition to an operating demonstration facility, the Acquisition Executive and the Energy System Acquisition Advisory Board (ESAAB) must concur in the facility's readiness to receive waste. This action, designated in DOE Order 4700.1 as Key Decision Four, concludes with the Chairman of the ESAAB issuing a Record of Decision. Since the meeting leading to the Record of Decision is scheduled for August 1988, plans must be made to ensure all activities contributing to that decision are completed in a clear and well-coordinated process. To support that effort, this Start-Up Plan was prepared to identify and track key events necessary to verify WIPP's readiness to receive waste; this provides a management/scheduling/tracking tool for the DOE WIPP Project Office (WPO) and a tracking mechanism for the DOE Albuquerque Operations Office (DOE-AL) and for DOE Headquarters (DOE-HQ); and describe the process to ensure readiness is documented by providing relevant data and reports to the cognizant decision makers. The methods by which these two purposes are achieved are discussed in further detail in the remainder of this plan

  9. Particle collection by a pilot plant venturi scrubber downstream from a pilot plant electrostatic precipitator

    Science.gov (United States)

    Sparks, L. E.; Ramsey, G. H.; Daniel, B. E.

    The results of pilot plant experiments of particulate collection by a venturi scrubber downstream from an electrostatic precipitator (ESP) are presented. The data, which cover a range of scrubber operating conditions and ESP efficiencies, show that particle collection by the venturi scrubber is not affected by the upstream ESP; i.e., for a given scrubber pressure drop, particle collection efficiency as a function of particle diameter is the same for both ESP on and ESP off. The experimental results are in excellent agreement with theoretical predictions. Order of magnitude cost estimates indicate that particle collection by ESP scrubber systems may be economically attractive when scrubbers must be used for SO x control.

  10. Pilot plant for flue gas treatment - continuous operation tests

    International Nuclear Information System (INIS)

    Chmielewski, A.G.; Tyminski, B.; Iller, E.; Zimek, Z.; Licki, J.; Radzio, B.

    1995-01-01

    Tests of continuous operation have been performed on pilot plant at EPS Kaweczyn in the wide range of SO 2 concentration (500-3000 ppm). The bag filter has been applied for aerosol separation. The high efficiencies of SO 2 and NO x removal, approximately 90% were obtained and influenced by such process parameters as: dose, gas temperature and ammonia stoichiometry. The main apparatus of the pilot plant (e.g. both accelerators) have proved their reliability in hard industrial conditions. (Author)

  11. Report on results for fiscal 1997 (B edition) on development of coal liquefaction technology. Development of bituminous coal liquefaction technology (research by pilot plant) 1/2; 1997 nendo sekitan ekika gijutsu kaihatsu seika hokokusho (B ban). Rekiseitan ekika gijutsu no kaihatsu (pilot plant ni yoru kenkyu) 2/2

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-06-01

    This paper reports the operation of a pilot plant of a bituminous coal liquefaction technology as the 1/2 report. The operation research of the Run-2 through the Run-4-2 was conducted using, as the material, tanitoharum coal which is operating basis coal. The Run-2 achieved a coal charging continuous operation for 42 days. During the operation of 80% slurry supply load, various data were obtained including material balance under the NEDOL standard liquefaction conditions, with a liquefaction yield of 54% daf coal achieved. Steam blowing into the heating tube was found effective as measures to cope with coking generation in the heating furnace of a vacuum distillation tower. The softening point of liquefaction residuals was improved to 178 degrees C through the extracting adjustment of reduced pressure heavy gravity light oil fraction for washing. The Run-3/4-1 achieved a plant load ratio of 100% and a long-term coal charging continuous operation for 80 days, while the Run-3 achieved a slurry supply load of 100% under the NEDOL standard liquefaction conditions. The Run-4-1 achieved a high liquefaction yield of 58wt% daf coal. Performance was confirmed of a neutron beam source irradiation apparatus/measuring system and a tracer injection equipment. (NEDO)

  12. Waste Isolation Pilot Plant Environmental Monitoring Plan

    International Nuclear Information System (INIS)

    2004-01-01

    U.S. Department of Energy (DOE) Order 450.1, Environmental Protection Program, requires each DOE site to conduct environmental monitoring. Environmental monitoring at the Waste Isolation Pilot Plant (WIPP) is conducted in order to: (a) Verify and support compliance with applicable federal, state, and local environmental laws, regulations, permits, and orders; (b) Establish baselines and characterize trends in the physical, chemical, and biological condition of effluent and environmental media; (c) Identify potential environmental problems and evaluate the need for remedial actions or measures to mitigate the problem; (d) Detect, characterize, and report unplanned releases; (e) Evaluate the effectiveness of effluent treatment and control, and pollution abatement programs; and (f) Determine compliance with commitments made in environmental impact statements, environmental assessments, safety analysis reports, or other official DOE documents. This Environmental Monitoring Plan (EMP) has been written to contain the rationale and design criteria for the monitoring program, extent and frequency of monitoring and measurements, procedures for laboratory analyses, quality assurance (QA) requirements, program implementation procedures, and direction for the preparation and disposition of reports. Changes to the environmental monitoring program may be necessary to allow the use of advanced technology and new data collection techniques. This EMP will document any proposed changes in the environmental monitoring program. Guidance for preparation of Environmental Monitoring Plans is contained in DOE/EH-0173T, Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance. The plan will be effective when it is approved by the appropriate Head of Field Organization or their designee. The plan discusses major environmental monitoring and hydrology activities at the WIPP and describes the programs established to ensure that WIPP operations do not

  13. Remote maintenance demonstration tests at a pilot plant for high level waste vitrification

    International Nuclear Information System (INIS)

    Selig, M.

    1984-01-01

    The remote maintenance and replacement technique designed for a radioactive vitrification plant have been developed and tested in a full scale handling mockup and in an inactive pilot plants by the Central Engineering Department of the Karlsruhe Nuclear Research Center. As a result of the development work and the tests it has been proved that the remote maintenance technique and remote handling equipment can be used without any technical problems and are suited for application in a radioactive waste vitrification plant

  14. Operation result of 40kW class MCFC pilot plant

    Energy Technology Data Exchange (ETDEWEB)

    Saitoh, H.; Hatori, S.; Hosaka, M.; Uematsu, H. [Ishikawajima-Harima Heavy Industries Co., Ltd., Tokyo (Japan)

    1996-12-31

    Ishikawajima-Harima Heavy Industries Co., Ltd. developed unique Molten Carbonate Fuel Cell (MCFC) system based on our original concept. To demonstrate the possibility of this system, based on MCFC technology of consigned research from New Energy and Industrial Technology Development Organization (NEDO) in Japan, we designed 40kW class MCFC pilot plant which had all equipments required as a power plant and constructed in our TO-2 Technical Center. This paper presents the test results of the plant.

  15. Encapsulation pilot plant of radioactive wastes in thermosetting resins

    International Nuclear Information System (INIS)

    1982-01-01

    The thermosetting resins (polyesters, epoxides) are used to encapsulate the low and intermediate - level radioactive wastes. The testing program concerning the drums produced by the pilot plant of the Chooz nuclear power plant is described. The installation operating is examined while thinking of the industrial application. The production costs are then evaluated

  16. FGD Franchising Pilot Project of Thermal Power Plants

    Institute of Scientific and Technical Information of China (English)

    2009-01-01

    According to the national policy on enhancing environmental protection,the five major power generation companies are required to carry out flue gas desulphurization(FGD) franchising pilot project in thermal power plants.This paper introduces the development of this pilot project,including the foundation,purpose,objects,demands and procedures.It also discusses some main problems encountered during implementation,involving the understanding,legislation,financing,taxation,pricing and management of franchise.At...

  17. The pilot plant for electron beam food processing

    International Nuclear Information System (INIS)

    Migdal, W.; Stachowicz, W.

    1993-01-01

    The investigations on food irradiation began in Poland in the end of 50-ties. Till the end of 70-ties the research activity on food irradiation was rather of the random nature and the objectives involved the fundamental research areas of food science. After the JECFI recommended in 1980 the general approval of foods treated with the doses of ionizing radiation up to 10 kG as unconditionally wholesome, the interest on practical application of food irradiation was gained in Poland. In 1986 the governmental bodies decided to recognize the possibilities of practical application of radiation techniques in agriculture, and the Central Research and Development Project No 10.13. ''Radiation Techniques in Agriculture'' was initiated for the period of 5 years. The project in the part that refers to food irradiations involved 3 major objectives: - radiation preservation of food; - radiation hygienization of animal feed; - Pilot plants for food irradiation. The most liable project of the programme was the construction of experimental plant for electron beam food irradiation, intended to be the national center for future testing and implementary works in this field. (orig.)

  18. Plant life management and modernisation: Research challenges in the EU

    International Nuclear Information System (INIS)

    Rintamaa, R.; Aho-Mantila, I.

    2010-01-01

    The NULIFE (Nuclear plant life prediction) European network of excellence is described in detail. The following topics are highlighted: Vision; Consortium; Organization and working methods; Research and development planning; Research project portfolio (pilot projects, umbrella projects); Strategic research planning; and Conclusions. (P.A.)

  19. Aquatic Plant Control Research Program

    National Research Council Canada - National Science Library

    Cofrancesco, Alfred

    1998-01-01

    .... This search for natural plant enemies (insects and fungal pathogens) has led researchers to the native ranges of noxious aquatic plants, located throughout the continents of Africa, Asia, Europe, and Australia...

  20. Prospects for pilot plants based on the tokamak, spherical tokamak and stellarator

    International Nuclear Information System (INIS)

    Menard, J.E.; Bromberg, L.; Brown, T.; Burgess, Thomas W.; Dix, D.; Gerrity, T.; Goldston, R.J.; Hawryluk, R.; Kastner, R.; Kessel, C.; Malang, S.; Minervini, J.; Neilson, G.H.; Neumeyer, C.L.; Prager, S.; Sawan, M.; Sheffield, J.; Sternlieb, A.; Waganer, L.; Whyte, D.G.; Zarnstorff, M.C.

    2011-01-01

    A potentially attractive next-step towards fusion commercialization is a pilot plant, i.e. a device ultimately capable of small net electricity production in as compact a facility as possible and in a configuration scalable to a full-size power plant. A key capability for a pilot-plant programme is the production of high neutron fluence enabling fusion nuclear science and technology (FNST) research. It is found that for physics and technology assumptions between those assumed for ITER and nth-of-a-kind fusion power plant, it is possible to provide FNST-relevant neutron wall loading in pilot devices. Thus, it may be possible to utilize a single facility to perform FNST research utilizing reactor-relevant plasma, blanket, coil and auxiliary systems and maintenance schemes while also targeting net electricity production. In this paper three configurations for a pilot plant are considered: the advanced tokamak, spherical tokamak and compact stellarator. A range of configuration issues is considered including: radial build and blanket design, magnet systems, maintenance schemes, tritium consumption and self-sufficiency, physics scenarios and a brief assessment of research needs for the configurations.

  1. Integrated automation system for a pilot plant for energy conversion using PEMFCs

    International Nuclear Information System (INIS)

    Culcer, Mihai; Iliescu, Mariana; Raceanu, Mircea; Stanciu, Vasile; Stefanescu, Ioan; Enache, Adrian; Lazaro, Pavel Gabriel; Lazaroiu, Gheorghe; Badea, Adrian

    2007-01-01

    Based on Hydrogen and Fuel Cells researches and technological capabilities achieved in the National R and D Programs, ICIT Rm. Valcea built an experimental-demonstrative pilot plant for energy conversion using hydrogen PEMFCs. This pilot plant consists of a fuel processor based on steam methane reforming (SMR) process, a hydrogen purification unit, a PEM fuel cells stack (FCS) and a power electronics unit. The paper deals with the dedicated controlling system that provides automated data acquisition, manual or on-line operational control, gas management, humidification, temperature and flow controls. (authors)

  2. The Waste Isolation Pilot Plant: a potential solution for the disposal of transuranic waste

    National Research Council Canada - National Science Library

    National Research Council Staff; Commission on Geosciences, Environment and Resources; Division on Earth and Life Studies; National Research Council; National Academy of Sciences

    ... Isolation Pilot Plant Board on Radioactive Waste Management Commission on Geosciences, Environment, and Resources National Research Council NATIONAL ACADEMY PRESS Washington, D.C. 1996 i Copyrighttrue Please breaks inserted. are Page files. accidentally typesetting been have may original from the errors not typographic original retained, and from the c...

  3. Electroosmotically enhanced sludge dewatering-pilot-plant study

    CSIR Research Space (South Africa)

    Smollen, M

    1994-01-01

    Full Text Available role in determining the ease or difficulty of phase separation. It seems that the inefficiency of dewatering applied to gelatinous and fine-particle sludges can be overcome by mechanical dewatering enhanced by electroosmosis. A prototype pilot-plant...

  4. Dissolution studies with pilot plant and actual INTEC calcines

    International Nuclear Information System (INIS)

    Herbst, R.S.; Garn, T.G.

    1999-01-01

    The dissolution of Idaho Nuclear Technology and Engineering Center (INTEC) pilot plant calcines was examined to determine solubility of calcine matrix components in acidic media. Two representatives pilot plant calcine types were studied: Zirconia calcine and Zirconia/Sodium calcine. Dissolution of these calcines was evaluated using lower initial concentrations of nitric acid than used in previous tests to decrease the [H+] concentration in the final solutions. Lower [H+] concentrations contribute to more favorable TRUEX/SREX solvent extraction flowsheet performance. Dissolution and analytical results were also obtained for radioactive calcines produced using high sodium feeds blended with non-radioactive Al(NO 3 ) 3 solutions to dilute the sodium concentration and prevent bed agglomeration during the calcination process. Dissolution tests indicated >95 wt.% of the initial calcine mass can be dissolved using the baseline dissolution procedure, with the exception that higher initial nitric acid concentrations are required. The higher initial acid concentration is required for stoichiometric dissolution of the oxides, primarily aluminum oxide. Statistically designed experiments using pilot plant calcine were performed to determine the effect of mixing rate on dissolution efficiency. Mixing rate was determined to provide minimal effects on wt.% dissolution. The acid/calcine ratio and temperature were the predominate variables affecting the wt.% dissolution, a result consistent with previous studies using other similar types of pilot plant calcines

  5. Rock mechanics activities at the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    Francke, C.; Saeb, S.

    1996-01-01

    The application of rock mechanics at nuclear waste repositories is a true multidisciplinary effort. A description and historical summary of the Waste Isolation Pilot Plant (WIPP) is presented. Rock mechanics programs at the WIPP are outlined, and the current rock mechanics modeling philosophy of the Westinghouse Waste Isolation Division is discussed

  6. Waste Isolation Pilot Plant Technical Assessment Team Report

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2015-03-17

    This report provides the results of the Waste Isolation Pilot Plant (WIPP) technical assessment led by the Savannah River National Laboratory and conducted by a team of experts in pertinent disciplines from SRNL and Lawrence Livermore National Laboratory (LLNL), Oak Ridge National Laboratory (ORNL), Pacific Northwest National Laboratory (PNNL), and Sandia National Laboratories (SNL).

  7. Analysis of Waste Isolation Pilot Plant Samples: Integrated Summary Report

    Energy Technology Data Exchange (ETDEWEB)

    Britt, Phillip F [ORNL

    2015-03-01

    Analysis of Waste Isolation Pilot Plant Samples: Integrated Summary Report. Summaries of conclusions, analytical processes, and analytical results. Analysis of samples taken from the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico in support of the WIPP Technical Assessment Team (TAT) activities to determine to the extent feasible the mechanisms and chemical reactions that may have resulted in the breach of at least one waste drum and release of waste material in WIPP Panel 7 Room 7 on February 14, 2014. This report integrates and summarizes the results contained in three separate reports, described below, and draws conclusions based on those results. Chemical and Radiochemical Analyses of WIPP Samples R-15 C5 SWB and R16 C-4 Lip; PNNL-24003, Pacific Northwest National Laboratory, December 2014 Analysis of Waste Isolation Pilot Plant (WIPP) Underground and MgO Samples by the Savannah River National Laboratory (SRNL); SRNL-STI-2014-00617; Savannah River National Laboratory, December 2014 Report for WIPP UG Sample #3, R15C5 (9/3/14); LLNL-TR-667015; Lawrence Livermore National Laboratory, January 2015 This report is also contained in the Waste Isolation Pilot Plant Technical Assessment Team Report; SRNL-RP-2015-01198; Savannah River National Laboratory, March 17, 2015, as Appendix C: Analysis Integrated Summary Report.

  8. Pilot plant for the radioactive decontamination of spent oils

    International Nuclear Information System (INIS)

    Flores E, R.M.; Ortiz O, H.V.; Cisneros L, L.; Lopez G, R.

    2002-01-01

    In this work the operation parameters obtained in the laboratory of oil storage are presented, as well as the operations which shape the pilot plant, the design criteria and the basic design of the core equipment of the developed process. Finally, the comparative results obtained the decontamination process of oil are given as well as laboratory scale. (Author)

  9. Radioactive Waste Treatment and Conditioning Using Plasma Technology Pilot Plant: Testing and Commissioning

    International Nuclear Information System (INIS)

    Rafizi Salihuddin; Rohyiza Baan; Norasalwa Zakaria

    2016-01-01

    Plasma pilot plant was commissioned for research and development program on radioactive waste treatment. The plant is equipped with a 50 kW direct current of non-transferred arc plasma torch which mounted vertically on top of the combustion chamber. The plant also consists of a dual function chamber, a water cooling system, a compress air supply system and a control system. This paper devoted the outcome after testing and commissioning of the plant. The problems arise was discussed in order to find the possible suggestion to overcome the issues. (author)

  10. Identification of Radioactive Pilot-Plant test requirements

    Energy Technology Data Exchange (ETDEWEB)

    Powell, W.J.; Riebling, E.F.

    1995-05-09

    Radioactive Pilot-Plant testing needs and alternatives are evaluated for enhanced Sludge Washing and High and Low-Level Vitrification efforts. Also investigated was instrument and equipment testing needs associated with the vitrification and retrieval process. The scope of this document is to record the existing March 1994 letter report for future use. A structured Kepner-Trego{trademark} decision analysis process was used to assist analysis of the testing needs. This analysis provided various combinations of laboratory and radioactive (hot) and cold pilot testing options associated with the above need areas. Recommendations for testing requirements were made.

  11. Identification of Radioactive Pilot-Plant test requirements

    International Nuclear Information System (INIS)

    Powell, W.J.; Riebling, E.F.

    1995-01-01

    Radioactive Pilot-Plant testing needs and alternatives are evaluated for enhanced Sludge Washing and High and Low-Level Vitrification efforts. Also investigated was instrument and equipment testing needs associated with the vitrification and retrieval process. The scope of this document is to record the existing March 1994 letter report for future use. A structured Kepner-Trego trademark decision analysis process was used to assist analysis of the testing needs. This analysis provided various combinations of laboratory and radioactive (hot) and cold pilot testing options associated with the above need areas. Recommendations for testing requirements were made

  12. Plant research '76

    Energy Technology Data Exchange (ETDEWEB)

    1976-01-01

    Overall objective remains unchanged: to contribute to the knowledge, with strong emphasis on fundamental problems, of how plants function, the roles they play in the environment and energy relations of the world, and how these roles may be optimized for the benefit of mankind. (PCS)

  13. Geomechanical applications for the Waste Isolation Pilot Plant (WIPP) project

    International Nuclear Information System (INIS)

    Matalucci, R.V.; Hunter, T.O.

    1981-01-01

    The Waste Isolation Pilot Plant (WIPP) is a research and development facility in bedded salt addressing the technical issues associated with the demonstration of disposal of radioactive waste from the defense programs of the USA. The geomechanical program includes laboratory experimentation, constitutive model and computer code development, and in-situ experimentation. Various material models, including creep for salt, and techniques for predicting room response under thermal and mechanical loads have been developed and are being applied to experiment and facility designs. A Benchmark II study has been conducted to compare the capabilities of nine structural codes to predict response of underground configuration under ambient temperature and with a thermal load of 7.5 W/m 2 . Parametric studies are being conducted to evaluate optimum room configurations. A series of in situ experiments is the next step towards validating models and predictive techniques. These experiments will be conducted in a facility in southeastern New Mexico mined at a depth of 659 m

  14. The waste isolation pilot plant: A new regulatory environment

    International Nuclear Information System (INIS)

    Frei, M.W.; Schneider, S.P.; Saris, E.C.; Austin, P.W.

    1993-01-01

    The US Department of Energy (DOE) is ready to embark on a multiyear test program, using radioactive waste, at the Waste Isolation Pilot Plant (WIPP). The WIPP is a deep geologic repository, constructed in ancient salt beds in southeastern New Mexico. It was authorized by Congress in 1979 as a research and development facility to demonstrate safe disposal of the nation's defense transuranic (TRU) waste. Nonradioactive testing in the repository has been under way for several years. The DOE is now ready to begin underground experiments at WIPP with small amounts of TRU waste. Radioactive waste testing in an actual repository environment will reduce uncertainties associated with predictions of long-term repository performance. However, the authority for DOE to begin this new phase of the test program no longer resides within the department. The WIPP is now subject to a new level of regulatory oversight by the Environmental Protection Agency (EPA) and other federal agencies, as set forth by Public Law 102-579, the WIPP Land Withdrawal Act, signed by the President on October 30, 1992. This paper discusses the act's new regulatory requirements for WIPP

  15. A historical review of Waste Isolation Pilot Plant backfill development

    International Nuclear Information System (INIS)

    Krumhansl, James L.; Molecke, Martin A.; Papenguth, Hans W.; Brush, Laurence H.

    2000-01-01

    Backfills have been part of Sandia National Laboratories' [Sandia's] Waste Isolation Pilot Plant [WIPP] designs for over twenty years. Historically, backfill research at Sandia has depended heavily on the changing mission of the WIPP facility. Early testing considered heat producing, high level, wastes. Bentonite/sand/salt mixtures were evaluated and studies focused on developing materials that would retard brine ingress, sorb radionuclides, and withstand elevated temperatures. The present-day backfill consists of pure MgO [magnesium oxide] in a pelletized form and is directed at treating the relatively low contamination level, non-heat producing, wastes actually being disposed of in the WIPP. Its introduction was motivated by the need to scavenging CO 2 [carbon dioxide] from decaying organic components in the waste. However, other benefits, such as a substantial desiccating capacity, are also being evaluated. The MgO backfill also fulfills a statutory requirement for assurance measures beyond those needed to demonstrate compliance with the US Environmental Protection Agency [EPA] regulatory release limits. However, even without a backfill, the WIPP repository design still operates within EPA regulatory release limits

  16. Groundwater monitoring at the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    Kehrman, R.; Broberg, K.; Tatro, G.; Richardson, R.; Dasczcyszak, W.

    1990-01-01

    This paper discusses the Groundwater Monitoring Program (GPM) being conducted at the Waste Isolation Pilot Plant (WIPP) in Carlsbad, New Mexico. The Regulatory and Environmental Programs (REP) section of the Environment, Safety and Health department (ES ampersand H) is responsible for conducting environmental monitoring at the WIPP. Groundwater monitoring is one of the ongoing environmental activities currently taking place. The REP section includes water quality sampling and water level monitoring. The WIPP Project is a research and develop facility designed to demonstrate the safe disposal of defense-generated waste in a geologic repository. Water quality sampling for physical, chemical, and radiological parameters has been an ongoing activity at the WIPP site for the past six years, and will continue through the life of the project. The water quality of a well is sampled while the well is continuously pumped. Serial samples of the pumped water are collected and tested for pH, Eh, temperature, specific gravity, specific conductivity, alkalinity, chlorides, divalent cations, ferrous iron, and total iron. Stabilization of serial sampling parameters determined if a representative sample is being obtained, Representative samples are sent to contract laboratories and analyzed for general chemistry, major cations and anions, and radionuclides. 13 refs., 4 figs., 1 tab

  17. MBR pilot plant for textile wastewater treatment and reuse.

    Science.gov (United States)

    Lubello, C; Caffaz, S; Mangini, L; Santianni, D; Caretti, C

    2007-01-01

    An experimental study was carried out in order to evaluate the possibility of upgrading the conventional activated sludge WWTP of Seano (Prato, Italy) which treats municipal and textile wastewaters, by using membrane bioreactor (MBR) technology. The MBR pilot plant, set up within Seano WWTP, was fed with mixed municipal-industrial wastewaters during the first experimental period and with pure industrial wastewaters during the second. Performances and operation of the MBR were evaluated in terms of permeate characteristics and variability (COD, colour, surfactants, total N and P) and other operational parameters (sludge growth and observed yield). According to the experimental results the MBR permeate quality was always superior to the Seano WWTP one and it was suitable for industrial reuse in the textile district of the Prato area. Respirometric tests provided a modified IWA ASM1 model which fits very well the experimental data and can be used for the design and the monitoring of a full-scale MBR pilot plant.

  18. Process control of an HTGR fuel reprocessing cold pilot plant

    International Nuclear Information System (INIS)

    Rode, J.S.

    1976-10-01

    Development of engineering-scale systems for a large-scale HTGR fuel reprocessing demonstration facility is currently underway in a cold pilot plant. These systems include two fluidized-bed burners, which remove the graphite (carbon) matrix from the crushed HTGR fuel by high temperature (900 0 C) oxidation. The burners are controlled by a digital process controller with an all analog input/output interface which has been in use since March, 1976. The advantages of such a control system to a pilot plant operation can be summarized as follows: (1) Control loop functions and configurations can be changed easily; (2) control constants, alarm limits, output limits, and scaling constants can be changed easily; (3) calculation of data and/or interface with a computerized information retrieval system during operation are available; (4) diagnosis of process control problems is facilitated; and (5) control panel/room space is saved

  19. A shaft seal system for the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    Hansen, F.D.; Ahrens, E.H.; Dennis, A.W.; Hurtado, L.D.; Knowles, M.K.; Tillerson, J.R.; Thompson, T.W.; Galbraith, D.

    1996-01-01

    As part of the demonstration of compliance with federal regulations, a shaft seal system has been designed for the Waste Isolation Pilot Plant. The system completely fills the 650 m shafts with components consisting of the common engineering materials, each of which possesses low permeability, longevity, and can be constructed using available technology. Design investigations couple rock mechanics and fluid flow analysis and tests of these materials within the natural geological setting, and demonstrate the effectiveness of the design

  20. Pilot-plant development of a Rover waste calcination flowsheet

    International Nuclear Information System (INIS)

    Birrer, S.A.

    1978-04-01

    Results of eight runs, six using the 10-cm dia and two using the 30-cm dia pilot-plant calciners, in which simulated first-cycle Rover waste was calcined, are described. Results of the tests showed that a feed blend consisting of one volume simulated first-cycle Rover waste and one or two volumes simulated first-cycle zirconium waste could not be successfully calcined. 5 figs., 8 tables

  1. Continuous precipitation of uranium peroxide in process pilot plant

    International Nuclear Information System (INIS)

    Quinelato, A.L.

    1990-01-01

    An experimental study on uranium peroxide precipitation has been carried out with the objective to evaluate the influence of the main process parameters with a technological approach. The uraniferous solution used was obtained from the hydrometallurgical processing of an ore from Itataia - CE. Studies were developed in two distinct experimental stages. In the first stage, the precipitation was investigated by means of laboratory batch tests and, in the second stage, by means of continuous operation in a process pilot plant. (author)

  2. Solar Pilot Plant project review No. 9, May 4--5, 1977. CDRL item 10

    Energy Technology Data Exchange (ETDEWEB)

    None

    1977-01-01

    Drawings and illustrations for the project review are presented. These are included for the 10 MW(e) solar pilot plant, the collector subsystem, the receiver subsystem, the electrical power generation system and balance of plant, plant controls and transient analysis, availability and safety, pilot and commercial plant designs, and summary and recommendations. (MHR)

  3. NOx Abatement Pilot Plant 90-day test results report

    International Nuclear Information System (INIS)

    McCray, J.A.; Boardman, R.D.

    1991-01-01

    High-level radioactive liquid wastes produced during nuclear fuel reprocessing at the Idaho Chemical Processing Plant are calcined in the New Waste Calcining Facility (NWCF) to provide both volume reduction and a more stable waste form. Because a large component of the HLW is nitric acid, high levels of oxides of nitrogen (NO x ) are produced in the process and discharged to the environment via the calciner off-gas. The NO x abatement program is required by the new Fuel Processing Restoration (FPR) project permit to construct to reduce NO x emissions from the NWCF. Extensive research and development has indicated that the selective catalytic reduction (SCR) process is the most promising technology for treating the NWCF off-gas. Pilot plant tests were performed to determine the compatibility of the SCR process with actual NWCF off-gas. Test results indicate that the SCR process is a viable method for abating the NO x from the NWCF off-gas. Reduction efficiencies over 95% can be obtained, with minimal amounts of ammonia slip, provided favorable operating conditions exist. Two reactors operated with series flow will provide optimum reduction capabilities. Typical operation should be performed with a first reactor stage gas space velocity of 20,000 hr -1 and an inlet temperature of 320 degrees C. The first stage exhaust NO x concentration will then dictate the parameter settings for the second stage. Operation should always strive for a peak reactor temperature of 520 degrees C in both reactors, with minimal NH 3 slip from the second reactor. Frequent fluctuations in the NWCF off-gas NO x concentration will require a full-scale reduction facility that is versatile and quick-responding. Sudden changes in NWCF off-gas NO x concentrations will require quick detection and immediate response to avoid reactor bed over-heating and/or excessive ammonia slip

  4. Technical Integration of SMART Pilot Plant

    Energy Technology Data Exchange (ETDEWEB)

    Kim, S. H.; Park, P. H.; Noh, P. C. (and others)

    2006-12-15

    Preliminary experimental tests were carried out using the thermal-hydraulic integral test facility, VISTA (Experimental Verification by Integral Simulation of Transients and Accidents), which has been constructed to simulate the SMART-P. The VISTA facility is an integral test facility including the primary and secondary systems as well as safety-related Passive Residual heat removal (PRHR) systems. The integrated SMART desalination plant consists of Multi Effect Distillation Process combined with Thermal-Vapor Compressor(MED-TVC) and coupled with the extracted steam from turbine through the steam transformer. Steam transformer produces the main pressure steam and supplies to the MED-TVC unit. MED-TVC was selected as a desalination process coupled with SMART, since the thermal vapor compression is very effective where the steam is available at high temperature and pressure conditions than required in the evaporator. The standard design of the SMART desalination plant is under development as a part of the SMART project. This report describes design concept of these systems and their requirements.

  5. First geothermal pilot power plant in Hungary

    Directory of Open Access Journals (Sweden)

    Tóth Anikó

    2007-01-01

    Full Text Available The Hungarian petroleum industry has always participated in the utilization of favourable geothermal conditions in the country. Most of the Hungarian geothermal wells were drilled by the MOL Ltd. as CH prospect holes. Accordingly, the field of geothermics belonged to the petroleum engineering, although marginally. It was therefore a surprise to hear of the decision of MOL Ltd. to build a geothermal power plant of about 2-5 MW. The tender was published in 2004.The site selected for the geothermal project is near the western border of an Hungarian oilfield, close to the Slovenian border. The location of the planned geothermal power plant was chosen after an analysis of suitable wells owned by the MOL Rt. The decision was made on the bases of different reservoir data. The existence of a reservoir of the necessary size, temperature, permeability, productivity and the water chemistry data was proved. The wells provide an enough information to understand the character of the reservoir and will be the production wells used by the planned power plant.The depth of the wells is about 2930 - 3200 m. The Triassic formation is reached at around 2851 m. The production and the reinjection wells are planned. The primary objective of the evaluation is to further learn the nature of the geothermal system. First a one-day discharge test is carried out. If this short-term test is successful, a six-months long-term discharge test will follow. The first period of the test is a transient phenomenon. Within the well test, the wellhead pressure, the flow rate, the outflowing water temperature, the dynamic fluid level, and the chemical components will be measured. The heat transfer around the bore-hole is influenced by the flow rate and the time. For the right appreciation of the measured data, it is very important to analyse the heat transfer processes around the bore-hole. The obtained data from the experiments must be also fitted into the framework of a mathematical

  6. Aquatic plant control research

    Energy Technology Data Exchange (ETDEWEB)

    Pryfogle, P.A.; Rinehart, B.N. [Idaho National Engineering Lab., Idaho Falls, ID (United States); Ghio, E.G. [Pacific Gas & Electric Company, San Francisco, CA (United States). Hydro Generation Engineering

    1997-05-01

    The Northwest region of the United States contains extensive canal systems that transport water for hydropower generation. Nuisance plants, including algae, that grow in these systems reduce their hydraulic capacity through water displacement and increased surface friction. Most control methods are applied in an ad hoc fashion. The goal of this work is to develop cost-effective, environmentally sound, long-term management strategies to prevent and control nuisance algal growth. This paper reports on a multi-year study, performed in collaboration with the Pacific Gas & Electric Company, to investigate algal growth in their canal systems, and to evaluate various control methodologies. Three types of controls, including mechanical, biological and chemical treatment, were selected for testing and evaluation. As part of this study, water quality data were collected and algal communities were sampled from numerous stations throughout the distribution system at regular intervals. This study resulted in a more comprehensive understanding of conditions leading to the development of nuisance algal growth, a better informed selection of treatment plans, and improved evaluation of the effectiveness for the control strategies selected for testing.

  7. Research Regarding High Gravity Brewing in the Pilot Station USAMV Cluj-Napoca

    Directory of Open Access Journals (Sweden)

    Andrei Borsa

    2013-11-01

    Full Text Available This paper aims to present preliminary research results obtained while developing and implementing a high gravity beer fermentation process. Production trials were performed in brewery pilot plant from University of Agricultural Sciences and Veterinary Medicine, Faculty of Food Science and Technology. The tehnological parameters were adapted and monitored during the making.

  8. Experimental investigation of the chemical looping method on a 1 MW pilot plant

    International Nuclear Information System (INIS)

    Orth, Matthias

    2014-01-01

    Attempting to counteract the consequences of climate change, leading industrial nations have agreed on reducing their CO 2 emissions significantly. To reach these reduction goals, it is essential to reduce the CO 2 emissions in the field of energy conversion. This PHD thesis covers the field of chemical looping combustion, a technology that uses fossil fuels for energy conversion with inherent capture of CO 2 . Since the research regarding chemical looping had so far focused mainly on lab scale or small scale experiments, a 1 MW pilot plant has been erected at Technische Universitaet Darmstadt in order to investigate the process in a semi-industrial scale and to check the process efficiency with commercially usable equipment. This pilot consists of two interconnected fluidized bed reactors and has an overall height of more than 11 m. In this thesis, some experiments with ilmenite - used as the oxygen carrier - are explained. Furthermore, the design, erection and commissioning of the pilot plant are presented as well as the results of the first test campaigns. The evaluation of the latter proves that the process can be handled in the design configuration and that CO 2 can be safely captured in a pilot plant of this scale.

  9. Radioactive waste disposal: Waste isolation pilot plants (WIPP). (Latest citations from the NTIS Bibliographic database). Published Search

    International Nuclear Information System (INIS)

    1993-09-01

    The bibliography contains citations concerning the Waste Isolation Pilot Plant (WIPP), a geologic repository located in New Mexico for transuranic wastes generated by the U.S. Government. Articles follow the development of the program from initial site selection and characterization through construction and testing, and examine research programs on environmental impacts, structural design, and radionuclide landfill gases. Existing plants and facilities, pilot plants, migration, rock mechanics, economics, regulations, and transport of wastes to the site are also included. The Salt Repository Project and the Crystalline Repository Project are referenced in separate bibliographies. (Contains a minimum of 228 citations and includes a subject term index and title list.)

  10. Experimental results: Pilot plant calcine dissolution and liquid feed stability

    International Nuclear Information System (INIS)

    Herbst, R.S.; Fryer, D.S.; Brewer, K.N.; Johnson, C.K.; Todd, T.A.

    1995-02-01

    The dissolution of simulated Idaho Chemical Processing Plant pilot plant calcines, containing none of the radioactive actinides, lanthanides or fission products, was examined to evaluate the solubility of calcine matrix materials in acidic media. This study was a necessary precursor to dissolution and optimization experiments with actual radionuclide-containing calcines. The importance of temperature, nitric acid concentration, ratio of acid volume to calcine mass, and time on the amount, as a weight percentage of calcine dissolved, was evaluated. These parameters were studied for several representative pilot plant calcine types: (1) Run No. 74 Zirconia calcine; (2) Run No. 17 Zirconia/Sodium calcine; (3) Run No. 64 Zirconia/Sodium calcine; (3) Run No. 1027 Alumina calcine; and (4) Run No. 20 Alumina/Zirconia/Sodium calcine. Statistically designed experiments with the different pilot plant calcines indicated the effect of the studied process variables on the amount of calcine dissolved decreases in the order: Acid/Calcine Ratio > Temperature > HNO 3 Concentration > Dissolution Time. The following conditions are suitable to achieve greater than 90 wt. % dissolution of most Zr, Al, or Na blend calcines: (1) Maximum nitric acid concentration of 5M; (2) Minimum acid/calcine ratio of 10 mL acid/1 gram calcine; (3) Minimum dissolution temperature of 90 degrees C; and (4) Minimum dissolution time of 30 minutes. The formation of calcium sulphate (CaSO 4 ) precipitates was observed in certain dissolved calcine solutions during the dissolution experiments. Consequently, a study was initiated to evaluate if and under what conditions the resulting dissolved calcine solutions would be unstable with regards to precipitate formation. The results indicate that precipitate formation in the calcine solutions prepared under the above proposed dissolution conditions are not anticipated

  11. The Waste Isolation Pilot Plant (WIPP) integrated project management system

    International Nuclear Information System (INIS)

    Olona, D.; Sala, D.

    1993-01-01

    The Waste Isolation Pilot Plant (WIPP), located 26 miles east of Carlsbad, New Mexico, is a research and development project of the Department of Energy (DOE), tasked with the mission of demonstrating the safe disposal of transuranic (TRU) radioactive wastes. This unique project was authorized by Congress in 1979 in response to the national need for long-term, safe methods for disposing of radioactive by-products from our national defense programs. The WIPP was originally established in December of 1979, by Public Law 96-164, DOE National Security and Military Applications of Nuclear Energy Authorization Act of 1980. Since the inception of the WIPP Project, work has continued to prepare the facility to receive TRU wastes. Studies continue to be conducted to demonstrate the safety of the WIPP facility in accordance with federal and state laws, state agreements, environmental regulations, and DOE Orders. The objectives of implementing an integrated project management system are to assure compliance with all regulatory and federal regulations, identify areas of concern, provide justification for funding, provide a management tool for control of program workscope, and establish a project baseline from which accountability and performance will be assessed. Program management and project controls are essential for the success of the WIPP Project. The WIPP has developed an integrated project management system to establish the process for the control of the program which has an expected total dollar value of $2B over the ten-year period from 1990-2000. The implementation of this project management system was motivated by the regulatory requirements of the project, the highly public environment in which the project takes place, limited funding and resources, and the dynamic nature of the project. Specific areas to be addressed in this paper include strategic planning, project organization, planning and scheduling, fiscal planning, and project monitoring and reporting

  12. Groundwater monitoring at the waste isolation pilot plant

    International Nuclear Information System (INIS)

    Kehrman, R.; Broberg, K.; Tatro, G.; Richardson, R.; Dasczcyszak, W.

    1990-01-01

    This paper discusses the Groundwater Monitoring Program (GMP) being conducted at the Waste Isolation Pilot Plant (WIPP) in Carlsbad, New Mexico. The Regulatory and Environmental Programs (REP) section of the Environment, Safety and Health department (ES ampersand H) is responsible for conducting environmental monitoring at the WIPP. Groundwater monitoring is one of the ongoing environmental activities currently taking place. The REP section includes water-quality sampling and water-level monitoring. The WIPP Project is a research and development facility designed to demonstrate the safe disposal of defense-generated TRU and mixed waste in a geologic repository. The Salado Formation of Permian age serves as the repository medium. The Salado Formation consists of bedded salt and associated evaporites. The formation is 602 meters thick at the site area; the top surface is located at a subsurface depth of 262 meters (10). The repository lies at a subsurface depth of 655 meters. Water-quality sampling for physical, chemical, and radiological parameters has been an ongoing activity at the WIPP site for the past six years, and will continue through the life of the project. Data collected from this program to date, has been used by Sandia National Laboratories for site characterization and performance assessment work. The data has also been used to establish a baseline of preoperational radiological and nonradiological groundwater quality. Once the facility begins receiving waste, this baseline will be used to determine if the WIPP facility influences or alters groundwater quality over time. The water quality of a well is determined while the well is continuously pumped. Serial samples of the pumped water are collected and tested for pH, Eh, temperature, specific gravity, specific conductivity, alkalinity, chlorides, divalent cations, ferrous iron, and total iron. 13 refs., 4 figs., 1 tab

  13. Report on results for fiscal 1997 (B edition) on development of coal liquefaction technology. Development of bituminous coal liquefaction technology (research by pilot plant) 1/2; 1997 nendo sekitan ekika gijutsu kaihatsu seika hokokusho (B gan). Rekiseitan ekika gijutsu no kaihatsu (pilot plant ni yoru kenkyu) 1/2

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-06-01

    Through the design, construction and operation of a pilot plant, the NEDOL method was verified, with its operation technology established, and also with a target set in collecting and accumulating data and knowledge required for a commercial plant in the future. With the Run-2, 3, 4 implemented using operating basis coal as the material, the operating stability of equipment/machines was confirmed, and a method of obtaining material balance as well as the operation technology was established, thereby demonstrating the NEDOL process, proving a long-term continuous operability and verifying the highest liquefaction yield. In addition, various process data, engineering data, operation control data, etc., were acquired, classified and analyzed. In the Run-3/4-1, a long-term coal charging continuous operation for 80 days was achieved, as was a high liquefaction yield of 58%. Moreover, data of material balance and thermal balance were obtained, with the performance confirmed of various kinds of equipment. Using the operating basis coat as the material, the coal charging operation of the Run-4-2 was commenced, with the performance verification test carried out for a neutron attenuation tracer method (NAT method), for the purpose of obtaining data of the flow characteristics of the liquefaction reaction tower. (NEDO)

  14. Technical Proposal Salton Sea Geothermal Power Pilot Plant Program

    Energy Technology Data Exchange (ETDEWEB)

    None

    1975-03-28

    The proposed Salton Sea Geothermal Power Pilot Plant Program comprises two phases. The objective of Phase 1 is to develop the technology for power generation from high-temperature, high-salinity geothermal brines existing in the Salton Sea known geothermal resources area. Phase 1 work will result in the following: (a) Completion of a preliminary design and cost estimate for a pilot geothermal brine utilization facility. (b) Design and construction of an Area Resource Test Facility (ARTF) in which developmental geothermal utilization concepts can be tested and evaluated. Program efforts will be divided into four sub-programs; Power Generation, Mineral Extraction, Reservoir Production, and the Area Resources Test Facility. The Power Generation Subprogram will include testing of scale and corrosion control methods, and critical power cycle components; power cycle selection based on an optimization of technical, environmental and economic analyses of candidate cycles; preliminary design of a pilot geothermal-electric generating station to be constructed in Phase 2 of this program. The Mineral Extraction Subprogram will involve the following: selection of an optimum mineral recovery process; recommendation of a brine clean-up process for well injection enhancement; engineering, construction and operation of mineral recovery and brine clean-up facilities; analysis of facility operating results from environmental, economical and technical point-of-view; preliminary design of mineral recovery and brine clean-up facilities of sufficient size to match the planned pilot power plant. The Reservoir Production Subprogram will include monitoring the operation and maintenance of brine production, handling and injection systems which were built with private funding in phase 0, and monitoring of the brine characteristics and potential subsidence effects during well production and injection. Based on the above, recommendations and specifications will be prepared for production and

  15. Cooperative Research Pilot Flatfish Survey (Yellowtail)

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — An industry-based pilot flatfish survey of Georges Bank conducted aboard the F/V Mary K and the F/V Yankee Pride. The surveyed used a two-seam, two-bridle flounder...

  16. Waste Isolation Pilot Plant CY 2000 Site Environmental Report

    International Nuclear Information System (INIS)

    Westinghouse TRU Solutions, LLC; Environmental Science and Research Foundation, Inc.

    2001-01-01

    The U.S. Department of Energy's (DOE) Carlsbad Field Office and Westinghouse TRU Solutions, LLC (WTS) are dedicated to maintaining high quality management of Waste Isolation Pilot Plant (WIPP) environmental resources. DOE Order 5400.1, General Environmental Protection Program, and DOE Order 231.1, Environmental, Safety, and Health Reporting, require that the environment at and near DOE facilities be monitored to ensure the safety and health of the public and the environment. This Waste Isolation Pilot Plant 2000 Site Environmental Report summarizes environmental data from calendar year (CY) 2000 that characterize environmental management performance and demonstrate compliance with federal and state regulations. This report was prepared in accordance with DOE Order 5400.1, DOE Order 231.1, the Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance (DOE/EH-0173T), and the Waste Isolation Pilot Plant Environmental Protect ion Implementation Plan (DOE/WIPP 96-2199). The above orders and guidance documents require that DOE facilities submit an Annual Site Environmental Report to DOE Headquarters, Office of the Assistant Secretary for Environment, Safety, and Health. The purpose of this report is to provide a comprehensive description of operational environmental monitoring activities, to provide an abstract of environmental activities conducted to characterize site environmental management performance to confirm compliance with environmental standards and requirements, and to highlight significant programs and efforts of environmental merit at WIPP during CY 2000. The format of this report follows guidance offered in a June 1, 2001 memo from DOE's Office of Policy and Guidance with the subject ''Guidance for the preparation of Department of Energy (DOE) Annual Site Environmental Reports (ASERs) for Calendar Year 2000.'' WIPP received its first shipment of waste on March 26, 1999. In 2000, no evidence was found of any adverse

  17. Waste Isolation Pilot Plant 2001 Site Environmental Report

    International Nuclear Information System (INIS)

    Westinghouse TRU Solutions, Inc.

    2002-01-01

    The United States (U.S.) Department of Energy's (DOE) Carlsbad Field Office (CBFO) and Westinghouse TRU Solutions LLC (WTS) are dedicated to maintaining high quality management of Waste Isolation Pilot Plant (WIPP) environmental resources. DOE Order 5400.1, General Environmental Protection Program, and DOE Order 231.1, Environmental, Safety, and Health Reporting, require that the environment at and near DOE facilities be monitored to ensure the safety and health of the public and the environment. This Waste Isolation Pilot Plant 2001 Site Environmental Report summarizes environmental data from calendar year (CY) 2001 that characterize environmental management performance and demonstrate compliance with federal and state regulations. This report was prepared in accordance with DOE Order 5400.1, DOE Order 231.1, the Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance (DOE/EH- 0173T), and the Waste Isolation Pilot Plant Environmental Protection Implementation Plan (DOE/WIPP 96-2199). The above Orders and guidance documents require that DOE facilities submit an annual site environmental report to DOE Headquarters, Office of the Assistant Secretary for Environment, Safety, and Health; and the New Mexico Environment Department (NMED). The purpose of this report is to provide a comprehensive description of operational environmental monitoring activities, to provide an abstract of environmental activities conducted to characterize site environmental management performance to confirm compliance with environmental standards and requirements, and to highlight significant programs and efforts of environmental merit at WIPP during CY 2001. WIPP received its first shipment of waste on March 26, 1999. In 2001, no evidence was found of any adverse effects from WIPP on the surrounding environment

  18. Waste Isolation Pilot Plant CY 2000 Site Environmental Report

    Energy Technology Data Exchange (ETDEWEB)

    Westinghouse TRU Solutions, LLC; Environmental Science and Research Foundation, Inc.

    2001-12-31

    The U.S. Department of Energy's (DOE) Carlsbad Field Office and Westinghouse TRU Solutions, LLC (WTS) are dedicated to maintaining high quality management of Waste Isolation Pilot Plant (WIPP) environmental resources. DOE Order 5400.1, General Environmental Protection Program, and DOE Order 231.1, Environmental, Safety, and Health Reporting, require that the environment at and near DOE facilities be monitored to ensure the safety and health of the public and the environment. This Waste Isolation Pilot Plant 2000 Site Environmental Report summarizes environmental data from calendar year (CY) 2000 that characterize environmental management performance and demonstrate compliance with federal and state regulations. This report was prepared in accordance with DOE Order 5400.1, DOE Order 231.1, the Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance (DOE/EH-0173T), and the Waste Isolation Pilot Plant Environmental Protect ion Implementation Plan (DOE/WIPP 96-2199). The above orders and guidance documents require that DOE facilities submit an Annual Site Environmental Report to DOE Headquarters, Office of the Assistant Secretary for Environment, Safety, and Health. The purpose of this report is to provide a comprehensive description of operational environmental monitoring activities, to provide an abstract of environmental activities conducted to characterize site environmental management performance to confirm compliance with environmental standards and requirements, and to highlight significant programs and efforts of environmental merit at WIPP during CY 2000. The format of this report follows guidance offered in a June 1, 2001 memo from DOE's Office of Policy and Guidance with the subject ''Guidance for the preparation of Department of Energy (DOE) Annual Site Environmental Reports (ASERs) for Calendar Year 2000.'' WIPP received its first shipment of waste on March 26, 1999. In 2000, no

  19. Waste Isolation Pilot Plant 1999 Site Environmental Report

    Energy Technology Data Exchange (ETDEWEB)

    Evans, Roy B.; Adams, Amy; Martin, Don; Morris, Randall C.; Reynolds, Timothy D.; Warren, Ronald W.

    2000-09-30

    The U.S. Department of Energy's (DOE)Carlsbad Area Office and the Westinghouse Waste Isolation Division (WID) are dedicated to maintaining high quality management of Waste Isolation Pilot Plant (WIPP) environmental resources. DOE Order 5400.1, General Environmental Protection Program, and DOE Order 231.1, Environmental, Safety, and Health Reporting, require that the environment at and near DOE facilities be monitored to ensure the safety and health of the public and the environment. This Waste Isolation Pilot Plant 1999 Site Environmental Report summarizes environmental data from calendar year 1999 that characterize environmental management performance and demonstrate compliance with federal and state regulations. This report was prepared in accordance with DOE Order 5400.1, DOE Order 231.1, the Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance (DOE/EH- 0173T), and the Waste Isolation Pilot Plant Environmental Protection Implementation Plan (DOE/WIPP 96-2199). The above orders and guidance documents require that DOE facilities submit an Annual Site Environmental Report to DOE Headquarters, Office of the Assistant Secretary for Environment, Safety, and Health. The purpose of this report is to provide a comprehensive description of operational environmental monitoring activities, to provide an abstract of environmental activities conducted to characterize site environmental management performance to confirm compliance with environmental standards and requirements, and to highlight significant programs and efforts of environmental merit at WIPP during calendar year 1999. WIPP received its first shipment of waste on March 26, 1999. In 1999, no evidence was found of any adverse effects from WIPP on the surrounding environment. Radionuclide concentrations in the environment surrounding WIPP were not statistically higher in 1999 than in 1998.

  20. Waste Isolation Pilot Plant 2001 Site Environmental Report

    Energy Technology Data Exchange (ETDEWEB)

    Westinghouse TRU Solutions, Inc.

    2002-09-20

    The United States (U.S.) Department of Energy's (DOE) Carlsbad Field Office (CBFO) and Westinghouse TRU Solutions LLC (WTS) are dedicated to maintaining high quality management of Waste Isolation Pilot Plant (WIPP) environmental resources. DOE Order 5400.1, General Environmental Protection Program, and DOE Order 231.1, Environmental, Safety, and Health Reporting, require that the environment at and near DOE facilities be monitored to ensure the safety and health of the public and the environment. This Waste Isolation Pilot Plant 2001 Site Environmental Report summarizes environmental data from calendar year (CY) 2001 that characterize environmental management performance and demonstrate compliance with federal and state regulations. This report was prepared in accordance with DOE Order 5400.1, DOE Order 231.1, the Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance (DOE/EH- 0173T), and the Waste Isolation Pilot Plant Environmental Protection Implementation Plan (DOE/WIPP 96-2199). The above Orders and guidance documents require that DOE facilities submit an annual site environmental report to DOE Headquarters, Office of the Assistant Secretary for Environment, Safety, and Health; and the New Mexico Environment Department (NMED). The purpose of this report is to provide a comprehensive description of operational environmental monitoring activities, to provide an abstract of environmental activities conducted to characterize site environmental management performance to confirm compliance with environmental standards and requirements, and to highlight significant programs and efforts of environmental merit at WIPP during CY 2001. WIPP received its first shipment of waste on March 26, 1999. In 2001, no evidence was found of any adverse effects from WIPP on the surrounding environment.

  1. Water Treatment Pilot Plant Design Manual: Low Flow Conventional/Direct Filtration Water Treatment Plant for Drinking Water Treatment Studies

    Science.gov (United States)

    This manual highlights the project constraints and concerns, and includes detailed design calculations and system schematics. The plant is based on engineering design principles and practices, previous pilot plant design experiences, and professional experiences and may serve as ...

  2. Waste Isolation Pilot Plant Site Environmental Report for calendar year 1989

    International Nuclear Information System (INIS)

    1989-01-01

    This is the 1989 Site Environmental Report (SER) for the Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico. The WIPP is a government owned and contractor-operated facility. The WIPP project is operated by Westinghouse Electric Corporation for the US Department of Energy (DOE). The mission of the WIPP is to provide a research and development facility to demonstrate the safe disposal of transuranic (TRU) waste generated by the defense activities of the US Government. This report provides a comprehensive description of environmental activities at the WIPP during calendar year 1989. The WIPP facility will not receive waste until all concerns affecting opening the WIPP are addressed to the satisfaction of the Secretary of Energy. Therefore, this report describes the status of the preoperational activities of the Radiological Environmental Surveillance (RES) program, which are outlined in the Radiological Baseline Program for the Waste Isolation Pilot Plant (WTSD-TME-057). 72 refs., 13 figs., 20 tabs

  3. Separation of packaging plastics by froth flotation in a continuous pilot plant

    International Nuclear Information System (INIS)

    Carvalho, Teresa; Durao, Fernando; Ferreira, Celia

    2010-01-01

    The objective of the research was to apply froth flotation to separate post-consumer PET (Polyethylene Terephthalate) from other packaging plastics with similar density, in a continuously operated pilot plant. A representative sample composed of 85% PET, 2.5% PVC (Polyvinyl Chloride) and 11.9% PS (Polystyrene) was subjected to a combination of alkaline treatment and surfactant adsorption followed by froth flotation. A mineral processing pilot plant, owned by a Portuguese mining company, was adapted for this purpose. The experimentation showed that it is possible to produce an almost pure concentrate of PET, containing 83% of the PET in feed, in a single bank of mechanical flotation cells. The concentrate grade attained was 97.2% PET, 1.1% PVC and 1.1% PS. By simulation it was shown that the Portuguese recycling industry specifications can be attained if one cleaning and one scavenger stages are added to the circuit.

  4. LEU fuel element produced by the Egyptian fuel manufacturing pilot plant

    International Nuclear Information System (INIS)

    Zidan, W.I.

    2000-01-01

    The Egyptian Fuel Manufacturing Pilot Plant, FMPP, is a Material Testing Reactor type (MTR) fuel element facility, for producing the specified fuel elements required for the Egyptian Second Research Reactor, ETRR-2. The plant uses uranium hexafluoride (UF 6 , 19.75% U 235 by wt) as a raw material which is processed through a series of the manufacturing, inspection and test plan to produce the final specified fuel elements. Radiological safety aspects during design, construction, operation, and all reasonably accepted steps should be taken to prevent or reduce the chance of accidents occurrence. (author)

  5. Pilot plant experience on high-level waste solidification and design of the engineering prototype VERA

    Energy Technology Data Exchange (ETDEWEB)

    Guber, W; Diefenbacher, W; Hild, W; Krause, H; Schneider, E; Schubert, G

    1972-11-01

    In the present paper the solidification process for highly active waste solutions as developed in the Karlsruhe Nuclear Research Center is presented. Its principal steps are: denitration, calcination in a spray calciner operated with superheated steam, melting of the calcine with appropriate additives to borosilicate glass in an induction-heated melting furnace. The operational experiences gained so far in the inactive 1:1 pilot plant are reported. Furthermore, a description is given of the projected multi-purpose experimental facility VERA 2 which is provided for processing the highly active waste solutions from the first German reprocessing plant WAK.

  6. Geotechnical Perspectives on the Waste Isolation Pilot Plant (WIPP)

    International Nuclear Information System (INIS)

    Francke, Chris T.; Hansen, Frank D.; Knowles, M. Kathyn; Patchet, Stanley J.; Rempe, Norbert T.

    1999-01-01

    The Waste Isolation Pilot Plant (WIPP) is the first nuclear waste repository certified by the United States Environmental Protection Agency. Success in regulatory compliance resulted from an excellent natural setting for such a repository, a facility with multiple, redundant safety systems, and from a rigorous, transparent scientific and technical evaluation. The WIPP story, which has evolved over the past 25 years, has generated a library of publications and analyses. Details of the multifaceted program are contained in the cited references. Selected geotechnical highlights prove the eminent suitability of the WIPP to serve its congressionally mandated purpose

  7. Hydrologic studies for the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    Davies, P.B.

    1994-01-01

    The objective of this paper is to provide a general overview of hydrologic conditions at the Waste Isolation Pilot Plant (WIPP) by describing several key hydrologic studies that have been carried out as part of the site characterization program over the last 20 years. The paper is composed of three parts: background information about general objectives of the WIPP project; information about the geologic and hydrologic setting of the facility; and information about three aspects of the hydrologic system that are important to understanding the long-term performance of the WIPP facility. For additional detailed information, the reader is referred to the references cited in the text

  8. Waste Isolation Pilot Plant Biennial Environmental Compliance Report

    Energy Technology Data Exchange (ETDEWEB)

    Washington Regulatory and Environmental Services (WRES)

    2004-10-25

    This Biennial Environmental Compliance Report (BECR) documents environmental regulatory compliance at the Waste Isolation Pilot Plant (WIPP), a facility designed and authorized for the safe disposal of transuranic (TRU) radioactive waste, for the reporting period of April 1, 2002, to March 31, 2004. As required by the WIPP Land Withdrawal Act (LWA) (Public Law [Pub. L.] 102-579, as amended by Pub. L. 104-201), the BECR documents U.S. Department of Energy (DOE) compliance with applicable environmental protection laws and regulations implemented by agencies of the federal government and the state of New Mexico.

  9. Operations Program Plan for the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    1990-09-01

    This document, Revision 4 of the Operations Program Plan, has been developed as the seven-year master plan for operating of the Waste Isolation Pilot Plant (WIPP). Subjects covered include public and technical communications; regulatory and environmental programs; startup engineering; radiation handling, surface operations, and underground operations; waste certification and waste handling; transportation development; geotechnical engineering; experimental operations; engineering program; general maintenance; security program; safety, radiation, and regulatory assurance; quality assurance program; training program; administration activities; management systems program; and decommissioning. 243 refs., 19 figs., 25 tabs. (SM)

  10. Waste Isolation Pilot Plant Annual Site Environmental Report for 2012

    Energy Technology Data Exchange (ETDEWEB)

    None

    2013-09-01

    The purpose of the Waste Isolation Pilot Plant (WIPP) Annual Site Environmental Report for 2012 (ASER) is to provide information required by U.S. Department of Energy (DOE) Order 231.1B, Environment, Safety, and Health Reporting. Specifically, the ASER presents summary environmental data to: Characterize site environmental management performance; Summarize environmental occurrences and responses reported during the calendar year; Confirm compliance with environmental standards and requirements; Highlight significant environmental accomplishments, including progress toward the DOE Environmental Sustainability Goals made through implementation of the WIPP Environmental Management System (EMS).

  11. The waste isolation pilot plant regulatory compliance program

    International Nuclear Information System (INIS)

    Mewhinney, J.A.; Kehrman, R.F.

    1996-01-01

    The passage of the WIPP Land Withdrawal Act of 1992 (LWA) marked a turning point for the Waste Isolation Pilot Plant (WIPP) program. It established a Congressional mandate to open the WIPP in as short a time as possible, thereby initiating the process of addressing this nation's transuranic (TRU) waste problem. The DOE responded to the LWA by shifting the priority at the WIPP from scientific investigations to regulatory compliance and the completion of prerequisites for the initiation of operations. Regulatory compliance activities have taken four main focuses: (1) preparing regulatory submittals; (2) aggressive schedules; (3) regulator interface; and (4) public interactions

  12. High Temperature Calcination - MACT Upgrade Equipment Pilot Plant Test

    Energy Technology Data Exchange (ETDEWEB)

    Richard D. Boardman; B. H. O& #39; Brien; N. R. Soelberg; S. O. Bates; R. A. Wood; C. St. Michel

    2004-02-01

    About one million gallons of acidic, hazardous, and radioactive sodium-bearing waste are stored in stainless steel tanks at the Idaho Nuclear Technology and Engineering Center (INTEC), which is a major operating facility of the Idaho National Engineering and Environmental Laboratory. Calcination at high-temperature conditions (600 C, with alumina nitrate and calcium nitrate chemical addition to the feed) is one of four options currently being considered by the Department of Energy for treatment of the remaining tank wastes. If calcination is selected for future processing of the sodium-bearing waste, it will be necessary to install new off-gas control equipment in the New Waste Calcining Facility (NWCF) to comply with the Maximum Achievable Control Technology (MACT) standards for hazardous waste combustors and incinerators. This will require, as a minimum, installing a carbon bed to reduce mercury emissions from their current level of up to 7,500 to <45 {micro}g/dscm, and a staged combustor to reduce unburned kerosene fuel in the off-gas discharge to <100 ppm CO and <10 ppm hydrocarbons. The staged combustor will also reduce NOx concentrations of about 35,000 ppm by 90-95%. A pilot-plant calcination test was completed in a newly constructed 15-cm diameter calciner vessel. The pilot-plant facility was equipped with a prototype MACT off-gas control system, including a highly efficient cyclone separator and off-gas quench/venturi scrubber for particulate removal, a staged combustor for unburned hydrocarbon and NOx destruction, and a packed activated carbon bed for mercury removal and residual chloride capture. Pilot-plant testing was performed during a 50-hour system operability test January 14-16, followed by a 100-hour high-temperature calcination pilot-plant calcination run January 19-23. Two flowsheet blends were tested: a 50-hour test with an aluminum-to-alkali metal molar ratio (AAR) of 2.25, and a 50-hour test with an AAR of 1.75. Results of the testing

  13. Waste Isolation Pilot Plant Biennial Environmental Compliance Report

    International Nuclear Information System (INIS)

    2004-01-01

    This Biennial Environmental Compliance Report (BECR) documents environmental regulatory compliance at the Waste Isolation Pilot Plant (WIPP), a facility designed and authorized for the safe disposal of transuranic (TRU) radioactive waste, for the reporting period of April 1, 2002, to March 31, 2004. As required by the WIPP Land Withdrawal Act (LWA) (Public Law [Pub. L.] 102-579, as amended by Pub. L. 104-201), the BECR documents U.S. Department of Energy (DOE) compliance with applicable environmental protection laws and regulations implemented by agencies of the federal government and the state of New Mexico.

  14. Research Note Pilot survey to assess sample size for herbaceous ...

    African Journals Online (AJOL)

    A pilot survey to determine sub-sample size (number of point observations per plot) for herbaceous species composition assessments, using a wheel-point apparatus applying the nearest-plant method, was conducted. Three plots differing in species composition on the Zululand coastal plain were selected, and on each plot ...

  15. Modeling temperature variations in a pilot plant thermophilic anaerobic digester.

    Science.gov (United States)

    Valle-Guadarrama, Salvador; Espinosa-Solares, Teodoro; López-Cruz, Irineo L; Domaschko, Max

    2011-05-01

    A model that predicts temperature changes in a pilot plant thermophilic anaerobic digester was developed based on fundamental thermodynamic laws. The methodology utilized two simulation strategies. In the first, model equations were solved through a searching routine based on a minimal square optimization criterion, from which the overall heat transfer coefficient values, for both biodigester and heat exchanger, were determined. In the second, the simulation was performed with variable values of these overall coefficients. The prediction with both strategies allowed reproducing experimental data within 5% of the temperature span permitted in the equipment by the system control, which validated the model. The temperature variation was affected by the heterogeneity of the feeding and extraction processes, by the heterogeneity of the digestate recirculation through the heating system and by the lack of a perfect mixing inside the biodigester tank. The use of variable overall heat transfer coefficients improved the temperature change prediction and reduced the effect of a non-ideal performance of the pilot plant modeled.

  16. Waste Isolation Pilot Plant Site Environmental Report Calendar Year 2002

    International Nuclear Information System (INIS)

    Washington Regulatory and Environmental Services

    2003-01-01

    The United States (U.S.) Department of Energy (DOE) Carlsbad Field Office (CBFO) and Washington TRU Solutions LLC (WTS) are dedicated to maintaining high quality management of Waste Isolation Pilot Plant (WIPP) environmental resources. DOE Order 5400.1, General Environmental Protection Program, and DOE Order 231.1, Environment, Safety, and Health Reporting, require that the environment at and near DOE facilities be monitored to ensure the safety and health of the public and the environment. This Waste Isolation Pilot Plant 2002 Site Environmental Report summarizes environmental data from calendar year 2002 that characterize environmental management performance and demonstrate compliance with federal and state regulations. This report was prepared in accordance with DOE Order 5400.1, DOE Order 231.1, and Guidance for the Preparation of DOE Annual Site Environmental Reports (ASERs) for Calendar Year 2002 (DOE Memorandum EH-41: Natoli:6-1336, April 4, 2003). These Orders and the guidance document require that DOE facilities submit an annual site environmental report to DOE Headquarters, Office of the Assistant Secretary for Environment, Safety, and Health; and the New Mexico Environment Department (NMED)

  17. Waste Isolation Pilot Plant Site Environmental Report Calendar Year 2002

    Energy Technology Data Exchange (ETDEWEB)

    Washington Regulatory and Environmental Services

    2003-09-17

    The United States (U.S.) Department of Energy (DOE) Carlsbad Field Office (CBFO) and Washington TRU Solutions LLC (WTS) are dedicated to maintaining high quality management of Waste Isolation Pilot Plant (WIPP) environmental resources. DOE Order 5400.1, General Environmental Protection Program, and DOE Order 231.1, Environment, Safety, and Health Reporting, require that the environment at and near DOE facilities be monitored to ensure the safety and health of the public and the environment. This Waste Isolation Pilot Plant 2002 Site Environmental Report summarizes environmental data from calendar year 2002 that characterize environmental management performance and demonstrate compliance with federal and state regulations. This report was prepared in accordance with DOE Order 5400.1, DOE Order 231.1, and Guidance for the Preparation of DOE Annual Site Environmental Reports (ASERs) for Calendar Year 2002 (DOE Memorandum EH-41: Natoli:6-1336, April 4, 2003). These Orders and the guidance document require that DOE facilities submit an annual site environmental report to DOE Headquarters, Office of the Assistant Secretary for Environment, Safety, and Health; and the New Mexico Environment Department (NMED).

  18. Arizona Public Service - Alternative Fuel (Hydrogen) Pilot Plant Design Report

    Energy Technology Data Exchange (ETDEWEB)

    James E. Francfort

    2003-12-01

    Hydrogen has promise to be the fuel of the future. Its use as a chemical reagent and as a rocket propellant has grown to over eight million metric tons per year in the United States. Although use of hydrogen is abundant, it has not been used extensively as a transportation fuel. To assess the viability of hydrogen as a transportation fuel and the viability of producing hydrogen using off-peak electric energy, Pinnacle West Capital Corporation (PNW) and its electric utility subsidiary, Arizona Public Service (APS) designed, constructed, and operates a hydrogen and compressed natural gas fueling station—the APS Alternative Fuel Pilot Plant. This report summarizes the design of the APS Alternative Fuel Pilot Plant and presents lessons learned from its design and construction. Electric Transportation Applications prepared this report under contract to the U.S. Department of Energy’s Advanced Vehicle Testing Activity. The Idaho National Engineering and Environmental Laboratory manages these activities for the Advanced Vehicle Testing Activity.

  19. The Stored Waste Examination Pilot Plant program at the INEL

    International Nuclear Information System (INIS)

    McKinley, K.B.; Anderson, B.C.; Clements, T.L.; Hinckley, J.P.; Mayberry, J.L.; Smith, T.H.

    1983-01-01

    Since 1970, defense transuranic waste has been placed into 20-year retrievable storage at the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory (INEL). A major objective of the U.S. Department of Energy (DOE) Nuclear Waste Management Program is to remove all retrievably stored transuranic waste from the INEL. The January 1981 DOE Record of Decision on the Waste Isolation Pilot Plant (WIPP) stated, ''The WIPP facility will dispose of defense transuranic waste stored retrievably at the Idaho National Engineering Laboratory.'' After retrieval and before shipment, processing may be necessary to prepare the waste for acceptance, handling, and enhanced long-term isolation in the WIPP. However, some of the waste is certifiable to the WIPP waste acceptance criteria without container opening or waste processing. To minimize costs, the Stored Waste Examination Pilot Plant (SWEPP) is being developed to certify INEL stored transuranic waste without container opening or waste processing. The SWEPP certification concept is based on records assessment, nondestructive examination techniques, assay techniques, health physics examinations, and limited opening of containers at another facility for quality control

  20. Guidebook on design, construction and operation of pilot plants for uranium ore processing

    International Nuclear Information System (INIS)

    1990-01-01

    The design, construction and operation of a pilot plant are often important stages in the development of a project for the production of uranium concentrates. Since building and operating a pilot plant is very costly and may not always be required, it is important that such a plant be built only after several prerequisites have been met. The main purpose of this guidebook is to discuss the objectives of a pilot plant and its proper role in the overall project. Given the wide range of conditions under which a pilot plant may be designed and operated, it is not possible to provide specific details. Instead, this book discusses the rationale for a pilot plant and provides guidelines with suggested solutions for a variety of problems that may be encountered. This guidebook is part of a series of Technical Reports on uranium ore processing being prepared by the IAEA's Division of Nuclear Fuel Cycle and Waste Management. 42 refs, 7 figs, 3 tabs

  1. Pilot incineration plant for solid, combustible, and low-level wastes

    International Nuclear Information System (INIS)

    Francioni, W.M.

    Radioactively contaminated wastes are formed in the handling of radioactive materials at the Federal Institute for Reactor Research (FIRR) and in other facilities, hospitals, sanitoria, industry, and nuclear power plants. A large part of the wastes are combustible and only very slightly radioactive. Incineration of these wastes is obvious. A pilot incineration plant, henceforth called the PIP, for radioactive combustible wastes of the FIRR is surveyed. The plant and its individual components are described. The production costs of the plant and experience gained in operation available at present are reviewed. Solid combustible radioactive waste can be incinerated in the PIP. The maximum possible reduction in volume of these wastes is achieved by incineration. Subsequently the chemically sterile ashes can be consolidated in a stable block suitable for long-term storage mixing with cement

  2. Conceptual design of SO3 decomposer for thermo-chemical iodine-sulfur process pilot plant

    International Nuclear Information System (INIS)

    Akihiro Kanagawa; Seiji Kasahara; Atsuhiko Terada; Shinji Kubo; Ryutaro Hino; Yoshiyuki Kawahara; Masaharu Watabe; Hiroshi Fukui; Kazuo Ishino; Toshio Takahashi

    2005-01-01

    Thermo-chemical water-splitting cycle is a method to make an effective use of the high temperature nuclear heat for hydrogen production. Japan Atomic Energy Research Institute (JAERI) has been conducting R and D on HTGR and also on thermo-chemical hydrogen production by using a thermo-chemical iodine-sulfur cycle (IS process). Based on the test results and know-how obtained through a bench-scale tests of hydrogen production of about 30 NL/hr, JAERI has a plan to construct a pilot test plant heated by high temperature helium gas, which has a hydrogen production performance of 30 Nm 3 /hr and will be operated under the high pressure up to 2 MPa. One of the key components of the pilot test plant is a SO 3 decomposer under high temperature conditions up to 850 degree C and high pressure up to 2 MPa. In this paper, a concept of the SO 3 decomposer for the pilot test plant fabricated with SiC ceramics, a corrosion-resistant material is investigated. Preliminary analyses on temperature and flow-rate distributions in the SO 3 decomposer and on thermal stress were carried out. A SO 3 decomposer model was experimentally manufactured. (authors)

  3. Select Generic Dry-Storage Pilot Plant Design for Safeguards and Security by Design (SSBD) per Used Fuel Campaign

    Energy Technology Data Exchange (ETDEWEB)

    Demuth, Scott Francis [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Sprinkle, James K. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2015-05-26

    As preparation to the year-end deliverable (Provide SSBD Best Practices for Generic Dry-Storage Pilot Scale Plant) for the Work Package (FT-15LA040501–Safeguards and Security by Design for Extended Dry Storage), the initial step was to select a generic dry-storage pilot plant design for SSBD. To be consistent with other DOE-NE Fuel Cycle Research and Development (FCR&D) activities, the Used Fuel Campaign was engaged for the selection of a design for this deliverable. For the work Package FT-15LA040501–“Safeguards and Security by Design for Extended Dry Storage”, SSBD will be initiated for the Generic Dry-Storage Pilot Scale Plant described by the layout of Reference 2. SSBD will consider aspects of the design that are impacted by domestic material control and accounting (MC&A), domestic security, and international safeguards.

  4. Prototype plant for nuclear process heat (PNP) - operation of the pilot plant for hydrogasification of coal

    International Nuclear Information System (INIS)

    Bruengel, N.; Dehms, G.; Fiedler, P.; Gerigk, H.P.; Ruddeck, W.; Schrader, L.; Schumacher, H.J.

    1988-04-01

    The Rheinische Braunkohlenwerke AG developed the process of hydrogasification of coal in a fluidized bed for generation of SNG. On basis of test results obtained in a semi-technical pilot plant of a through-put of 250 kg/h dried coal a large pilot plant was erected processing 10 t/h dried brown coal. This plant was on stream for about 14700 h, of which about 7800 h were with gasifier operation; during this time about 38000 t of dried brown coal of the Rhenish district were processed containing 4 to 25% of ash. At pressures of 60 to 120 bar and temperatures of 800 to 935 0 C carbon conversion rates up to 81 percent and methane amounts of 5000 m 3 (STP)/h were reached. The decisive parameter for methane generation was the hydrogen/coal-ratio. Even at high moisture contents, usually diminishing the methane yield from the coal essentially, by high hydrogen/coal-ratios high methane yields could be obtained. The gasifier itself caused no troubles during the total time operation. Difficulties with the original design of the residual char cooler could be overcome by change-over from water injection to liquid carbon dioxide. The design of the heat recovery system proved well. Alltogether so the size increasement of the gasifier from the semi-technical to the large pilot plant as well as the harmonization of gas generation and gas refining was proved. (orig.) With 20 refs., 20 tabs., 81 figs [de

  5. Waste Isolation Pilot Plant Safety Analysis Report. Volume 5

    International Nuclear Information System (INIS)

    1986-01-01

    This Safety Analysis Report (SAR) has been prepared by the US Department of Energy (DOE) to support the construction and operation of the Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico. The WIPP facility is designed to receive, inspect, emplace, and store unclassified defense-generated transuranic wastes in a retrievable fashion in an underground salt medium and to conduct studies and perform experiments in salt with high-level wastes. Upon the successful completion of these studies and experiments, WIPP is designed to serve as a permanent facility. The first chapter of this report provides a summary of the location and major design features of WIPP. Chapters 2 through 5 describe the site characteristics, design criteria, and design bases used in the design of the plant and the plant operations. Chapter 6 discusses radiation protection; Chapters 7 and 8 present an accident analysis of the plant and an assessment of the long-term waste isolation at WIPP. The conduct of operations and operating controls and limits are discussed in Chapters 9 and 10. The quality assurance programs are described in Chapter 11

  6. Waste Isolation Pilot Plant Safety Analysis Report. Volume 1

    International Nuclear Information System (INIS)

    1986-01-01

    This Safety Analysis Report (SAR) has been prepared by the US Department of Energy (DOE) to support the construction and operation of the Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico. The WIPP facility is designed to receive, inspect, emplace, and store unclassified defense-generated transuranic wastes in a retrievable fashion in an underground salt medium and to conduct studies and perform experiments in salt with high-level wastes. Upon the successful completion of these studies and experiments, WIPP is designed to serve as a permanent facility. The first chapter of this report provides a summary of the location and major design features of WIPP. Chapters 2 through 5 describe the site characteristics, design criteria, and design bases used in the design of the plant and the plant operations. Chapter 6 discusses radiation protection: Chapters 7 and 8 present an accident analysis of the plant and an assessment of the long-term waste isolation at WIPP. The conduct of operations and operating control and limits are discussed in Chapters 9 and 10. The quality assurance programs are described in Chapter 11

  7. Waste Isolation Pilot Plant Safety Analysis Report. Volume 4

    International Nuclear Information System (INIS)

    1986-01-01

    This Safety Analysis Report (SAR) has been prepared by the US Department of Energy (DOE) to support the construction and operation of the Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico. The WIPP facility is designed to receive, inspect, emplace, and store unclassified defense-generated transuranic wastes in a retrievable fashion in an underground salt medium and to conduct studies and perform experiments in salt with high-level wastes. Upon the successful completion of these studies and experiments, WIPP is designed to serve as a permanent facility. The first chapter of this report provides a summary of the location and major design features of WIPP. Chapters 2 through 5 describe the site characteristics, design criteria, and design bases used in the design of the plant and the plant operations. Chapter 6 discusses radiation protection; Chapters 7 and 8 present an accident analysis of the plant and an assessment of the long-term waste isolation at WIPP. The conduct of operations and operating controls and limits are discussed in Chapters 9 and 10. The quality assurance programs are described in Chapter 11

  8. Waste Isolation Pilot Plant Safety Analysis Report. Volume 2

    International Nuclear Information System (INIS)

    1986-01-01

    This Safety Analysis Report (SAR) has been prepared by the US Department of Energy (DOE) to support the construction and operation of the Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico. The WIPP facility is designed to receive, inspect, emplace, and store unclassified defense-generated transuranic wastes in a retrievable fashion in an underground salt medium and to conduct studies and perform experiments in salt with high-level wastes. Upon the successful completion of these studies and experiments, WIPP is designed to serve as a permanent facility. The first chapter of this report provides a summary of the location and major design features of WIPP. Chapters 2 through 5 describe the site characteristics, design criteria, and design bases used in the design of the plant and the plant operations. Chapter 6 discusses radiation protection; Chapters 7 and 8 present an accident analysis of the plant and an assessment of the long-term waste isolation at WIPP. The conduct of operations and operating controls and limits are discussed in Chapters 9 and 10. The quality assurance programs are described in Chapter 11

  9. Nuclear plant aging research program

    International Nuclear Information System (INIS)

    Eissenberg, D.M.

    1987-01-01

    The U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, has established the Nuclear Plant Aging Research (NPAR) program in its Division of Engineering Technology. Principal contractors for this program include Oak Ridge National Laboratory, Brookhaven National Laboratory, Idaho National Engineering Laboratory, and Pacific Northwest Laboratory. The program goals are: to identify and characterize time-dependent degradation (aging) of nuclear plant safety-related electrical and mechanical components which could lead to loss of safety function; to identify and recommend methods for detecting and trending aging effects prior to loss of safety function so that timely maintenance can be implemented; and to recommend maintenance practices for mitigating the effects of aging. Research activities include prioritization of system and component aging in nuclear plants, characterization of aging degradation of specific components including identification of functional indicators useful for trending degradation, and testing of practical methods and devices for measuring the functional indicators. Aging assessments have been completed on electric motors, snubbers, motor-operated valves, and check valves. Testing of trending methods and devices for motor-operated valves and check valves is in progress

  10. Pilot plant production at Riso of LEU silicide fuel for the Danish reactor DR3

    International Nuclear Information System (INIS)

    Toft, P.; Borring, J.; Adolph, E.

    1988-01-01

    A pilot plant for fabricating LEU silicide fuel elements has been established at Riso National Laboratory. Three test elements for the Danish reactor DR3 have been fabricated, based on 19.88% enriched U 3 Si 2 powder that has been purchased elsewhere. The pilot plant has been set up and 3 test elements fabricated without any major difficulties

  11. The significance of the pilot conditioning plant (PKA) for spent fuel management

    International Nuclear Information System (INIS)

    Willax, H.O.

    1996-01-01

    The pilot conditioning plant (PKA) is intended as a multi-purpose facility and thus may serve various purposes involved in the conditioning or disposal of spent fuel elements or radwaste. Its design as a pilot plant permits development and trial of various methods and processes for fuel element conditioning, as well as for radwaste conditioning. (orig./DG) [de

  12. General Atomic HTGR fuel reprocessing pilot plant: results of initial sequential equipment operation

    International Nuclear Information System (INIS)

    1978-09-01

    In September 1977, the processing of 20 large high-temperature gas-cooled reactor (LHTGR) fuel elements was completed sequentially through the head-end cold pilot plant equipment. This report gives a brief description of the equipment and summarizes the results of the sequential operation of the pilot plant. 32 figures, 15 tables

  13. Tetrafluoride uranium pilot plant in operation at IEA, using the moving bed process

    International Nuclear Information System (INIS)

    Franca Junior, J.M.

    1975-01-01

    A UF 4 pilot plant, in operation at IEA, using the moving bed process is reported. UO 3 obtained from the thermal decomposition of ADU is used as a starting material in this pilot plant. The type of equipment and the process are both described. Ammonia gas (NH 3 ) was used in the reduction operation and anhydrous hydrofluoric acid (HF) in the hydrofluorination step

  14. Sharing five years of pilot plant experience on aromatics extraction with ionic liquids

    NARCIS (Netherlands)

    Onink, S.A.F.; Hansmeier, A.R.; Meindersma, G.W.; Haan, de A.B.

    2011-01-01

    Since 2004 pilot plant trials have been conducted with various contactors and different ionic liquids for petrochemical model feeds as well as real refinery feeds. Our pilot plant contains several columns (rotating disc contactor, Kuhni, pulsed disc and donut column) with a height of 6 m and 5 cm

  15. Long term pilot plant experience on aromatics extraction with ionic liquids

    NARCIS (Netherlands)

    Meindersma, W.G.W.; Onink, F.S.A.F.; Hansmeier, A.R.; Haan, de A.B.

    2012-01-01

    Since 2004, we have been conducting pilot plant trials with various contactors and different ionic liquids for petrochemical model feeds as well as real refinery feeds. Our pilot plant contains a Rotating Disc Contactor with a height of 6 m and a diameter of 60 mm. Up to 100 kg of ionic liquid and

  16. Arsenic pilot plant operation and results:Weatherford, Oklahoma.

    Energy Technology Data Exchange (ETDEWEB)

    Aragon, Malynda Jo; Arora, H. (Narasimhan Consulting Services Inc., Phoenix, Arizona); Karori, Saqib (Narasimhan Consulting Services Inc., Phoenix, Arizona); Pathan, Sakib (Narasimhan Consulting Services Inc., Phoenix, Arizona)

    2007-05-01

    Narasimhan Consulting Services, Inc. (NCS), under a contract with the Sandia National Laboratories (SNL), designed and operated pilot scale evaluations of the adsorption and coagulation/filtration treatment technologies aimed at meeting the recently revised arsenic maximum contaminant level (MCL) for drinking water. The standard of 10 {micro}g/L (10 ppb) is effective as of January 2006. The pilot demonstration is a project of the Arsenic Water Technology Partnership program, a partnership between the American Water Works Association Research Foundation (AwwaRF), SNL and WERC (A Consortium for Environmental Education and Technology Development). The pilot evaluation was conducted at Well 30 of the City of Weatherford, OK, which supplies drinking water to a population of more than 10,400. Well water contained arsenic in the range of 16 to 29 ppb during the study. Four commercially available adsorption media were evaluated side by side for a period of three months. Both adsorption and coagulation/filtration effectively reduced arsenic from Well No.30. A preliminary economic analysis indicated that adsorption using an iron oxide media was more cost effective than the coagulation/ filtration technology.

  17. Recent trends in medicinal plants research

    National Research Council Canada - National Science Library

    Shyur, Lie-fen; Lau, Allan S.Y

    2012-01-01

    .... One type of research explores the value of medicinal plants as traditionally used and studies of these plants have the potential to determine which plants are most potent, optimize dosages and dose...

  18. Bentonite as a waste isolation pilot plant shaft sealing material

    International Nuclear Information System (INIS)

    Daemen, J.; Ran, Chongwei

    1996-12-01

    Current designs of the shaft sealing system for the Waste Isolation Pilot Plant (WIPP) propose using bentonite as a primary sealing component. The shaft sealing designs anticipate that compacted bentonite sealing components can perform through the 10,000-year regulatory period and beyond. To evaluate the acceptability of bentonite as a sealing material for the WIPP, this report identifies references that deal with the properties and characteristics of bentonite that may affect its behavior in the WIPP environment. This report reviews published studies that discuss using bentonite as sealing material for nuclear waste disposal, environmental restoration, toxic and chemical waste disposal, landfill liners, and applications in the petroleum industry. This report identifies the physical and chemical properties, stability and seal construction technologies of bentonite seals in shafts, especially in a saline brine environment. This report focuses on permeability, swelling pressure, strength, stiffness, longevity, and densification properties of bentonites

  19. Bentonite as a waste isolation pilot plant shaft sealing material

    Energy Technology Data Exchange (ETDEWEB)

    Daemen, J.; Ran, Chongwei [Univ. of Nevada, Reno, NV (United States)

    1996-12-01

    Current designs of the shaft sealing system for the Waste Isolation Pilot Plant (WIPP) propose using bentonite as a primary sealing component. The shaft sealing designs anticipate that compacted bentonite sealing components can perform through the 10,000-year regulatory period and beyond. To evaluate the acceptability of bentonite as a sealing material for the WIPP, this report identifies references that deal with the properties and characteristics of bentonite that may affect its behavior in the WIPP environment. This report reviews published studies that discuss using bentonite as sealing material for nuclear waste disposal, environmental restoration, toxic and chemical waste disposal, landfill liners, and applications in the petroleum industry. This report identifies the physical and chemical properties, stability and seal construction technologies of bentonite seals in shafts, especially in a saline brine environment. This report focuses on permeability, swelling pressure, strength, stiffness, longevity, and densification properties of bentonites.

  20. Waste Isolation Pilot Plant Groundwater Protection Management Program Plan

    Energy Technology Data Exchange (ETDEWEB)

    Washington TRU Solutions

    2002-09-24

    U.S. Department of Energy (DOE) Order 5400.1, General Environmental Protection Program, requires each DOE site to prepare a Groundwater Protection Management Program Plan. This document fulfills the requirement for the Waste Isolation Pilot Plant (WIPP). This document was prepared by the Hydrology Section of the Westinghouse TRU Solutions LLC (WTS) Environmental Compliance Department, and it is the responsibility of this group to review the plan annually and update it every three years. This document is not, nor is it intended to be, an implementing document that sets forth specific details on carrying out field projects or operational policy. Rather, it is intended to give the reader insight to the groundwater protection philosophy at WIPP.

  1. Final environmental impact statement. Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    1980-10-01

    This volume contains the appendices for the Final Environmental Impact Statement for the Waste Isolation Pilot Plant (WIPP). Alternative geologic environs are considered. Salt, crystalline rock, argillaceous rock, and tuff are discussed. Studies on alternate geologic regions for the siting of WIPP are reviewed. President Carter's message to Congress on the management of radioactive wastes and the findings and recommendations of the interagency review group on nuclear waste management are included. Selection criteria for the WIPP site including geologic, hydrologic, tectonic, physicochemical compatability, and socio-economic factors are presented. A description of the waste types and the waste processing procedures are given. Methods used to calculate radiation doses from radionuclide releases during operation are presented. A complete description of the Los Medanos site, including archaeological and historic aspects is included. Environmental monitoring programs and long-term safety analysis program are described

  2. Waste Isolation Pilot Plant Annual Site Environmental Report for 2016

    Energy Technology Data Exchange (ETDEWEB)

    Ward, Anderson [Carlsbad Field Office (CBFO), NM (United States); Basabilvazo, George T. [Carlsbad Field Office (CBFO), NM (United States)

    2017-09-01

    The purpose of the Waste Isolation Pilot Plant (WIPP) Annual Site Environmental Report for 2016 (ASER) is to provide the information required by U.S. Department of Energy (DOE) Order 231.1B, Environment, Safety, and Health Reporting. The DOE Carlsbad Field Office (CBFO) and the management and operating contractor (MOC) maintain and preserve the environmental resources at the WIPP facility. DOE Order 231.1B; DOE Order 436.1, Departmental Sustainability; and DOE Order 458.1, Radiation Protection of the Public and the Environment, require that the affected environment at and near DOE facilities be monitored to ensure the safety and health of the public and workers, and preservation of the environment. This report was prepared in accordance with DOE Order 231.1B, which requires DOE facilities to submit an ASER to the DOE Headquarters Chief Health, Safety, and Security Officer.

  3. Waste Isolation Pilot Plant Groundwater Protection Management Program Plan

    International Nuclear Information System (INIS)

    1993-01-01

    The DOE has mandated in DOE Order 5400.1 that its operations will be conducted in an environmentally safe manner. The Waste Isolation Pilot Plant (WIPP) will comply with DOE Order 5400.1 and will conduct its operations in a manner that ensures the safety of the environment and the public. This document outlines how the WIPP will protect and preserve groundwater within and surrounding the WIPP facility. Groundwater protection is just one aspect of the WIPP environmental protection effort. The WIPP groundwater surveillance program is designed to determine statistically if any changes are occurring in groundwater characteristics within and surrounding the WIPP facility. If a change is noted, the cause will be determined and appropriate corrective action initiated

  4. Annual stability evaluation of Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    1993-06-01

    A stability evaluation of the underground workings of the Waste Isolation Pilot Plant (WIPP) was completed by the US Bureau of Mines' WIPP evaluation committee. This work included a critical evaluation of the processes employed at WIPP to ensure stability, an extensive review of available deformation measurements, a 3-day site visit, and interviews with the Department of Energy (DOE) and Westinghouse staff. General ground control processes are in place at WIPP to minimize the likelihood that major stability problems will go undetected. To increase confidence in both short- and long-term stability throughout the site (underground openings and shafts), ground stability monitoring systems, mine layout design, support systems and data analyses must be continuously improved. Such processes appear to be in place at WIPP and are discussed in this paper

  5. Cold flow model study of an oxyfuel combustion pilot plant

    Energy Technology Data Exchange (ETDEWEB)

    Guio-Perez, D.C.; Tondl, G.; Hoeltl, W.; Proell, T.; Hofbauer, H. [Vienna University of Technology, Institute of Chemical Engineering, Vienna (Austria)

    2011-12-15

    The fluid-dynamic behavior of a circulating fluidized bed pilot plant for oxyfuel combustion was studied in a cold flow model, down-scaled using Glicksman's criteria. Pressures along the unit and the global circulation rate were used for characterization. The analysis of five operating parameters and their influence on the system was carried out; namely, total solids inventory and the air velocity of primary, secondary, loop seal and support fluidizations. The cold flow model study shows that the reactor design allows stable operation at a wide range of fluidization rates, with results that agree well with previous observations described in the literature. (Copyright copyright 2011 WILEY-VCH Verlag GmbH and Co. KGaA, Weinheim)

  6. Revised concept for the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    Dennis, A.W.; Milloy, J.A.; Scully, L.W.; Shefelbine, H.C.; Stinebaugh, R.E.; Wowak, W.E.

    1978-07-01

    The quantities of remotely handled wastes that must be handled at the Waste Isolation Pilot Plant have been reduced from 250 x 10 3 ft 3 /y to 10 x 10 3 ft 3 /y; the capital cost of the facility will be reduced from 534 to 428 million dollars. Changes in the facility design due to the reduction in the amount of remote-handled waste are discussed. If DOE should exercise its option to construct a high-level waste repository concurrently with the construction of the revised design, with both facilities receiving waste in 1985, the combined cost would be about 580 million dollars. However, it is unlikely that significant quantities of high-level waste in a form suitable for geologic disposal would be available until after 1990. (13 figures, 5 tables)

  7. WIPP [Waste Isolation Pilot Plant] test phase plan: Performance assessment

    International Nuclear Information System (INIS)

    1990-04-01

    The U.S. Department of Energy (DOE) is responsible for managing the disposition of transuranic (TRU) wastes resulting from nuclear weapons production activities of the United States. These wastes are currently stored nationwide at several of the DOE's waste generating/storage sites. The goal is to eliminate interim waste storage and achieve environmentally and institutionally acceptable permanent disposal of these TRU wastes. The Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico is being considered as a disposal facility for these TRU wastes. This document describes the first of the following two major programs planned for the Test Phase of WIPP: Performance Assessment -- determination of the long-term performance of the WIPP disposal system in accordance with the requirements of the EPA Standard; and Operations Demonstration -- evaluation of the safety and effectiveness of the DOE TRU waste management system's ability to emplace design throughput quantities of TRU waste in the WIPP underground facility. 120 refs., 19 figs., 8 tabs

  8. Environmental Impact Statement: Waste Isolation Pilot Plant (WIPP): Executive summary

    International Nuclear Information System (INIS)

    1980-10-01

    The purpose of this document is to provide a summary of the environmental impact statement for the Waste Isolation Pilot Plant (WIPP) project. The Draft Environmental Impact Statement for the WIPP was published by the US Department of Energy (DOE) in April 1979. This document was reviewed and commented on by members of the general public, private organizations, and governmental agencies. The Final Environmental Impact Statement was subsequently published in October, 1980. This summary is designed to assist decision-maker and interested individuals in reviewing the material presented in the environmental impact statement for the WIPP project. To make this material widely available, this summary is published in both Spanish and English. Additional, more detailed information concerning the environmental and safety consequences of the WIPP project is available in the Final Environmental Impact Statement. Written comments and public hearing comments on the Draft Environmental Impact Statement are available for review. 27 refs., 4 figs., 7 tabs

  9. Final environmental impact statement. Waste Isolation Pilot Plant

    Energy Technology Data Exchange (ETDEWEB)

    1980-10-01

    This volume contains the appendices for the Final Environmental Impact Statement for the Waste Isolation Pilot Plant (WIPP). Alternative geologic environs are considered. Salt, crystalline rock, argillaceous rock, and tuff are discussed. Studies on alternate geologic regions for the siting of WIPP are reviewed. President Carter's message to Congress on the management of radioactive wastes and the findings and recommendations of the interagency review group on nuclear waste management are included. Selection criteria for the WIPP site including geologic, hydrologic, tectonic, physicochemical compatability, and socio-economic factors are presented. A description of the waste types and the waste processing procedures are given. Methods used to calculate radiation doses from radionuclide releases during operation are presented. A complete description of the Los Medanos site, including archaeological and historic aspects is included. Environmental monitoring programs and long-term safety analysis program are described. (DMC)

  10. Waste Isolation Pilot Plant in situ experimental program for HLW

    International Nuclear Information System (INIS)

    Molecke, M.A.

    1977-01-01

    The Waste Isolation Pilot Plant (WIPP) will be a facility to demonstrate the environmental and operational safety of storing radioactive wastes in a deep geologic bedded salt facility. The WIPP will be located in southeastern New Mexico, approximately 30 miles east of the city of Carlsbad. The major focus of the pilot plant operation involves ERDA defense related low and intermediate-level transuranic wastes. The scope of the project also specifically includes experimentation utilizing commercially generated high-level wastes, or alternatively, spent unreprocessed fuel elements. WIPP HLW experiments are being conducted in an inter-related laboratory, bench-scale, and in situ mode. This presentation focuses on the planned in situ experiments which, depending on the availability of commercially reprocessed waste plus delays in the construction schedule of the WIPP, will begin in approximately 1985. Such experiments are necessary to validate preceding laboratory results and to provide actual, total conditions of geologic storage which cannot be adequately simulated. One set of planned experiments involves emplacing bare HLW fragments into direct contact with the bedded salt environment. A second set utilizes full-size canisters of waste emplaced in the salt in the same manner as planned for a future HLW repository. The bare waste experiments will study in an accelerated manner waste-salt bed-brine interactions including matrix integrity/degradation, brine leaching, system chemistry, and potential radionuclide migration through the salt bed. Utilization of full-size canisters of HLW in situ permits us to demonstrate operational effectiveness and safety. Experiments will evaluate corrosion and compatibility interactions between the waste matrix, canister and overpack materials, getter materials, stored energy, waste buoyancy, etc. Using full size canisters also allows us to demonstrate engineered retrievability of wastes, if necessary, at the end of experimentation

  11. Test phase plan for the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    1993-03-01

    The US Department of Energy (DOE) has prepared this Test Phase Plan for the Waste Isolation Pilot Plant to satisfy the requirements of Public Law 102-579, the Waste Isolation Pilot Plant (WIPP) Land Withdrawal Act (LWA). The Act provides seven months after its enactment for the DOE to submit this Plan to the Environmental Protection Agency (EPA) for review. A potential geologic repository for transuranic wastes, including transuranic mixed wastes, generated in national-defense activities, the WIPP is being constructed in southeastern New Mexico. Because these wastes remain radioactive and chemically hazardous for a very long time, the WIPP must provide safe disposal for thousands of years. The DOE is developing the facility in phases. Surface facilities for receiving waste have been built and considerable underground excavations (2150 feet below the surface) that are appropriate for in-situ testing, have been completed. Additional excavations will be completed when they are required for waste disposal. The next step is to conduct a test phase. The purpose of the test phase is to develop pertinent information and assess whether the disposal of transuranic waste and transuranic mixed waste in the planned WIPP repository can be conducted in compliance with the environmental standards for disposal and with the Solid Waste Disposal Act (SWDA) (as amended by RCRA, 42 USC. 6901 et. seq.). The test phase includes laboratory experiments and underground tests using contact-handled transuranic waste. Waste-related tests at WIPP will be limited to contact-handled transuranic and simulated wastes since the LWA prohibits the transport to or emplacement of remote-handled transuranic waste at WIPP during the test phase

  12. Waste Isolation Pilot Plant Biennial Environmental Compliance Report

    Energy Technology Data Exchange (ETDEWEB)

    Westinghouse TRU Solutions

    2000-12-01

    This Biennial Environmental Compliance Report (BECR) documents environmental regulatory compliance at the Waste Isolation Pilot Plant (WIPP), a facility designed for the safe disposal of transuranic (TRU) radioactive waste, for the reporting period of April 1, 1998, to March 31, 2000. As required by the WIPP Land Withdrawal Act (LWA)(Public Law [Pub. L.] 102-579, and amended by Pub. L. 104-201), the BECR documents U.S. Department of Energy (DOE) Carlsbad Area Office's (hereinafter the ''CAO'') compliance with applicable environmental protection laws and regulations implemented by agencies of the federal government and the state of New Mexico. An issue was identified in the 1998 BECR relating to a potential cross-connection between the fire-water systems and the site domestic water system. While the CAO and its managing and operating contractor (hereinafter the ''MOC'') believe the site was always in compliance with cross-connection control requirements, hardware and procedural upgrades w ere implemented in March 1999 to strengthen its compliance posture. Further discussion of this issue is presented in section 30.2.2 herein. During this reporting period WIPP received two letters and a compliance order alleging violation of certain requirements outlined in section 9(a)(1) of the LWA. With the exception of one item, pending a final decision by the New Mexico Environment Department (NMED), all alleged violations have been resolved without the assessment of fines or penalties. Non-mixed TRU waste shipments began on March 26, 1999. Shipments continued through November 26, 1999, the effective date of the Waste Isolation Pilot Plant Hazardous Waste Facility Permit (NM4890139088-TSDF). No shipments regulated under the Hazardous Waste Facility Permit were received at WIPP during this BECR reporting period.

  13. Waste Isolation Pilot Plant Biennial Environmental Compliance Report

    International Nuclear Information System (INIS)

    Westinghouse TRU Solutions

    2000-01-01

    This Biennial Environmental Compliance Report (BECR) documents environmental regulatory compliance at the Waste Isolation Pilot Plant (WIPP), a facility designed for the safe disposal of transuranic (TRU) radioactive waste, for the reporting period of April 1, 1998, to March 31, 2000. As required by the WIPP Land Withdrawal Act (LWA)(Public Law [Pub. L.] 102-579, and amended by Pub. L. 104-201), the BECR documents U.S. Department of Energy (DOE) Carlsbad Area Office's (hereinafter the ''CAO'') compliance with applicable environmental protection laws and regulations implemented by agencies of the federal government and the state of New Mexico. An issue was identified in the 1998 BECR relating to a potential cross-connection between the fire-water systems and the site domestic water system. While the CAO and its managing and operating contractor (hereinafter the ''MOC'') believe the site was always in compliance with cross-connection control requirements, hardware and procedural upgrades w ere implemented in March 1999 to strengthen its compliance posture. Further discussion of this issue is presented in section 30.2.2 herein. During this reporting period WIPP received two letters and a compliance order alleging violation of certain requirements outlined in section 9(a)(1) of the LWA. With the exception of one item, pending a final decision by the New Mexico Environment Department (NMED), all alleged violations have been resolved without the assessment of fines or penalties. Non-mixed TRU waste shipments began on March 26, 1999. Shipments continued through November 26, 1999, the effective date of the Waste Isolation Pilot Plant Hazardous Waste Facility Permit (NM4890139088-TSDF). No shipments regulated under the Hazardous Waste Facility Permit were received at WIPP during this BECR reporting period

  14. Pilot studies of management of ageing of nuclear power plant instrumentation and control components

    International Nuclear Information System (INIS)

    Burnay, S.G.; Simola, K.; Kossilov, A.; Pachner, J.

    1993-01-01

    This paper describes pilot studies which have been implemented to study the aging behavior of safety related component parts of nuclear power plants. In 1989 the IAEA initiated work on pilot studies related to the aging of such components. Four components were identified for study. They are the primary nozzle of a reactor vessel; a motor operated isolating valve; the concrete containment building; and instrumentation and control cables within the containment facility. The study was begun with phase 1 efforts directed toward understanding the aging process, and methods for monitoring and minimizing the effects of aging. Phase 2 efforts are directed toward aging studies, documentation of the ideas put forward, and research to answer questions identified in phase 1. This paper describes progress made on two of these components, namely the motor operated isolation valves, and in-containment I ampersand C cables

  15. Deep shaft high rate aerobic digestion: laboratory and pilot plant performance

    Energy Technology Data Exchange (ETDEWEB)

    Tran, F; Gannon, D

    1981-01-01

    The Deep Shaft is essentially an air-lift reactor, sunk deep in the ground (100-160 m); the resulting high hydrostatic pressure together with very efficient mixing in the shaft provide extremely high O transfer efficiencies (O.T.E.) of less than or equal to 90% vs. 4-20% in other aerators. This high O.T.E. suggests real potential for Deep-Shaft technology in the aerobic digestion of sludges and animal wastes: with conventional aerobic digesters an O.T.E. over 8% is extremely difficult to achieve. Laboratory and pilot plant Deep-Shaft aerobic digester studies carried out at Eco-Research's Pointe Claire, Quebec laboratories, and at the Paris, Ontario pilot Deep-Shaft digester are described.

  16. A mixed method pilot study: the researchers' experiences.

    Science.gov (United States)

    Secomb, Jacinta M; Smith, Colleen

    2011-08-01

    This paper reports on the outcomes of a small well designed pilot study. Pilot studies often disseminate limited or statistically meaningless results without adding to the body knowledge on the comparative research benefits. The design a pre-test post-test group parallel randomised control trial and inductive content analysis of focus group transcripts was tested specifically to increase outcomes in a proposed larger study. Strategies are now in place to overcome operational barriers and recruitment difficulties. Links between the qualitative and quantitative arms of the proposed larger study have been made; it is anticipated that this will add depth to the final report. More extensive reporting on the outcomes of pilot studies would assist researchers and increase the body of knowledge in this area.

  17. A pilot modeling technique for handling-qualities research

    Science.gov (United States)

    Hess, R. A.

    1980-01-01

    A brief survey of the more dominant analysis techniques used in closed-loop handling-qualities research is presented. These techniques are shown to rely on so-called classical and modern analytical models of the human pilot which have their foundation in the analysis and design principles of feedback control. The optimal control model of the human pilot is discussed in some detail and a novel approach to the a priori selection of pertinent model parameters is discussed. Frequency domain and tracking performance data from 10 pilot-in-the-loop simulation experiments involving 3 different tasks are used to demonstrate the parameter selection technique. Finally, the utility of this modeling approach in handling-qualities research is discussed.

  18. A pilot plant for solar-cell manufacture; Ligne pilote de fabrication de cellules solaires

    Energy Technology Data Exchange (ETDEWEB)

    Fischer, D.; Ziegler, Y.; Closset, A. [VHF - Technologies SA, Yverdon-les-Bains (Switzerland)

    2005-07-01

    A pilot plant for the manufacture of amorphous silicon solar cells on plastic film substrate was built allowing the annual production of 40 kW peak power. The production steps comprise: a) the continuous coating of n-i-p solar cells by VHF-PECVD with a capacity of 28.5 meters in 8.5 hours; b) transparent-conducting-oxide (TCO) top contact structuring using a continuous process; c) series connection step (scribing and Ag-paste) with a capacity of 28 meters in 6 hours; d) back and top contact sputtering with 3 parallel magnetrons; e) integration of a large-area vacuum laminator enabling the simultaneous lamination of 4 products of 4 Wp. In parallel with this project, a complete cost model was established enabling a more quantitative approach of the future technological and industrial strategy of the company. An increase of the capacity to 100 kWp has been planned for summer 2005.

  19. The working of RVNRL pilot plant of Rubber Board and it's safety devices

    International Nuclear Information System (INIS)

    Britto, I.J.; Thomas, E.V.

    1996-01-01

    A pilot plant for producing radiation vulcanized natural rubber latex (RVNRL) was established at Rubber Board, India in 1992. Irradiation is done by a batch process in the plant. The plant has a versatile safety system for safety of operators and people working in and around the plant

  20. Pilot Research Summaries, 1967-1970.

    Science.gov (United States)

    Casey, James L.; Hayes, Larry K.

    This report contains one-page summaries of a majority of the 134 research studies funded through the Oklahoma Consortium on Research Development. The research covers the whole spectrum of academic topics , from nursing to ecology to art to politics.. Brief summaries of a majority of the 37 development seminars funded through the Consortium are…

  1. Pilot plant studies of the bioconversion of cellulose and production of ethanol

    Energy Technology Data Exchange (ETDEWEB)

    Wilke, C.R.

    1977-01-31

    Progress is reported in several areas of research. The following cellulosic raw materials were selected for study: wheat, barley, and rice straws, rice hulls, sorghum, corn stover, cotton gin trash, newsprint, ground wood, and masonite steam-treated Douglas fir and redwood. Samples were collected, prepared, and analyzed for hexosans, pentosans, lignin, ash, and protein. Results of acid extraction and enzymatic hydrolysis are discussed. Yields of glucose, polyglucose, xylose, and arabinose are reported. Progress in process design and economic studies, as well as pilot plant process development and design studies, is summarized. (JGB)

  2. Solvent Refined Coal (SRC) process: trace elements. Research and development report No. 53, interim report No. 31, August 1976-July 1977. Volume III. Pilot plant development work. Part 6

    International Nuclear Information System (INIS)

    1980-03-01

    Results are presented on a study of the distribution and fate of 34 trace elements in the Solvent Refined Coal Process at the pilot plant located at Fort Lewis, Washington, and operated by The Pittsburg and Midway Coal Mining Co. under contract with the US Department of Energy. Neutron activation analysis was used to determine Ti, V, Ca, Mg, Al, Cl, Mn, As, Sb, Se, Hg, Br, Co, Ni, Cr, Fe, Na, Rb, Cs, K, Sc, Tb, Eu, Sm, Ce, La, Sr, Ba, Th, Hf, Ta, Ga, Zr, and Cu in feed coals, process solvent, Solvent Refined Coal (SRC), mineral residues, wet filter cake, by-product solvents, process and effluent waters and by-product sulfur. The sample points were chosen such that the major process streams were adequately described and that the major input and output materials were included. Atomic absorption spectrophotometry was used to measure the toxic elements Pb, Cd, Be in plant-derived solvents, effluent water and Hamer Marsh water. Specific methods were developed for analysis of a wide range of material compositions. The neutron activation analysis procedures were divided into short and long irradiation procedures for elements with short half lives (less than 3 hours) and intermediate to long half lives ( 8 hours to 5.2 years). Data are presented for a third equilibrium set of samples from the SRC-I process and compared to two similar sets analyzed previously. A material balance (or budget) was calculated for each element from the concentration data and the yields of each process fraction. Data are also presented on a study of carbon monoxide addition to the hydrogen stream and its effect on trace elements, and trace element data on a study of thirty-six plant effluent water samples taken during an SRC-I production run

  3. Preliminary design needs for pilot plant of Monazite processing into Thorium Oxide (ThO_2)

    International Nuclear Information System (INIS)

    Hafni Lissa Nuri; Prayitno; Abdul Jami; M-Pancoko

    2014-01-01

    Data and information collection aimed in order to meet the needs of the initial design for pilot plant of monazite processing into thorium oxide (ThO_2). The content of thorium in monazite is high in Indonesia between 2.9 to 4.1% and relatively abundant in Bangka Belitung Islands. Thorium can be used as fuel because of its potential is more abundant instead of uranium. Plant of thorium oxide commercially from monazite established starting from pilot uranium. Plant of thorium oxide commercially from monazite established starting from pilot plant in order to test laboratory data. Pilot plant design started from initial design, basic design, detailed design, procurement and construction. Preliminary design needs includes data feed and products, a block diagram of the process, a description of the process, the determination of process conditions and type of major appliance has been conducted. (author)

  4. General Atomic Reprocessing Pilot Plant: engineering-scale dissolution system description

    International Nuclear Information System (INIS)

    Yip, H.H.

    1979-04-01

    In February 1978, a dissolver-centrifuge system was added to the cold reprocessing pilot plant at General Atomic Company, which completed the installation of an HTGR fuel head-end reprocessing pilot plant. This report describes the engineering-scale equipment in the pilot plant and summarizes the design features derived from development work performed in the last few years. The dissolver operating cycles for both thorium containing BISO and uranium containinng WAR fissile fuels are included. A continuous vertical centrifuge is used to clarify the resultant dissolver product solution. Process instrumentation and controls for the system reflect design philosophy suitable for remote operation

  5. The UCOR pilot plant and the development of axial flow compressors

    International Nuclear Information System (INIS)

    Grant, W.

    1984-01-01

    This article discusses some of the mechanical aspects of the Uranium Enrichment Corporation of South Africa (Pty) Ltd. (UCOR) pilot plant. The most important mechanical components in a typical stage in the pilot plant, consists of a compressor which is used to compress the process gas mixture. After air cooling to almost room temperature, the mixture is fed through the separation elements. Other components are two pressure vessels connected to the compressor. The development and characteristics of the pilot plant is described in the article

  6. Desind an operation of pilot plant production of biodisel fron frying oils

    Directory of Open Access Journals (Sweden)

    Nelly Morales Pedraza

    2008-06-01

    Full Text Available The objective of this article is present the pilot plant used in the research titled: Production of biodiesel from used edible oils to industrial level for the production of methyl or ethyl esters from vegetable oils used in the food industry that be used as a fuel in diesel engines type, in order to generate alternative use for these oils are reused, and additionally, generate new options in biofuels that can replace methyl ester, since these need of methanol, a product that usually is a derived petrochemical and highly toxic. In this small-scale plant for the production of ethyl esters (biodiesel can be evaluated spent oils of different kinds and diverse origin, or study oils from food industries, which are usually a blend of palm oil and soybean oil, and other times palm oils hydrogenated or mixtures of oil spent with palm oil refning RBD (refned, bleached and deodorized. The results are the basis for the design and construction of a pilot plant to produce biodiesel by lot of 6 liter by hour approximately, which is evaluated under simulated conditions of loading and operation. It was designed and implemented a batch reactor with heating and stirring mechanics, drivers with temperature, condensation and total alcohol refux, maintaining a molar relationship of 6:1 (alcohol/oil, which is considered the best relation for a esterification with basic catalysis several scientifc publications. The temperature of the reaction is set at 60 °C and atmospheric pressure. The productivity of the reaction

  7. Waste Isolation Pilot Plant Annual Site Enviromental Report for 2008

    International Nuclear Information System (INIS)

    2009-01-01

    The purpose of the Waste Isolation Pilot Plant Annual Site Environmental Report for 2008 (ASER) is to provide information required by U.S. Department of Energy (DOE) Order 231.1A, Environment, Safety, and Health Reporting. Specifically, the ASER presents summary environmental data to characterize site environmental management performance; summarize environmental occurrences and responses reported during the calendar year; confirm compliance with environmental standards and requirements; highlight significant facility programs and efforts; and describe how compliance and environmental improvement is accomplished through the WIPP Environmental Management System (EMS). The DOE Carlsbad Field Office (CBFO) and the management and operating contractor (MOC), Washington TRU Solutions LLC (WTS), maintain and preserve the environmental resources at the Waste Isolation Pilot Plant (WIPP). DOE Order 231.1A; DOE Order 450.1A, Environmental Protection Program; and DOE Order 5400.5, Radiation Protection of the Public and the Environment, require that the affected environment at and near DOE facilities be monitored to ensure the safety and health of the public and workers, and preservation of the environment. This report was prepared in accordance with DOE Order 231.1A, which requires that DOE facilities submit an ASER to the DOE Headquarters Chief Health, Safety, and Security Officer. The WIPP Hazardous Waste Facility Permit (HWFP) Number NM4890139088-TSDF (treatment, storage, and disposal facility) further requires that the ASER be provided to the New Mexico Environment Department (NMED). The WIPP mission is to safely dispose of transuranic (TRU) radioactive waste generated by the production of nuclear weapons and other activities related to the national defense of the United States. In 2008, 5,265 cubic meters (m3) of TRU waste were disposed of at the WIPP facility, including 5,216 m3 of contact-handled (CH) TRU waste and 49 m3 of remote-handled (RH) TRU waste. From the first

  8. Waste Isolation Pilot Plant Annual Site Enviromental Report for 2008

    Energy Technology Data Exchange (ETDEWEB)

    Washington Regulatory and Enviromnetal Services

    2009-09-21

    The purpose of the Waste Isolation Pilot Plant Annual Site Environmental Report for 2008 (ASER) is to provide information required by U.S. Department of Energy (DOE) Order 231.1A, Environment, Safety, and Health Reporting. Specifically, the ASER presents summary environmental data to characterize site environmental management performance; summarize environmental occurrences and responses reported during the calendar year; confirm compliance with environmental standards and requirements; highlight significant facility programs and efforts; and describe how compliance and environmental improvement is accomplished through the WIPP Environmental Management System (EMS). The DOE Carlsbad Field Office (CBFO) and the management and operating contractor (MOC), Washington TRU Solutions LLC (WTS), maintain and preserve the environmental resources at the Waste Isolation Pilot Plant (WIPP). DOE Order 231.1A; DOE Order 450.1A, Environmental Protection Program; and DOE Order 5400.5, Radiation Protection of the Public and the Environment, require that the affected environment at and near DOE facilities be monitored to ensure the safety and health of the public and workers, and preservation of the environment. This report was prepared in accordance with DOE Order 231.1A, which requires that DOE facilities submit an ASER to the DOE Headquarters Chief Health, Safety, and Security Officer. The WIPP Hazardous Waste Facility Permit (HWFP) Number NM4890139088-TSDF (treatment, storage, and disposal facility) further requires that the ASER be provided to the New Mexico Environment Department (NMED). The WIPP mission is to safely dispose of transuranic (TRU) radioactive waste generated by the production of nuclear weapons and other activities related to the national defense of the United States. In 2008, 5,265 cubic meters (m3) of TRU waste were disposed of at the WIPP facility, including 5,216 m3 of contact-handled (CH) TRU waste and 49 m3 of remote-handled (RH) TRU waste. From the first

  9. Research on the enhancement of biological nitrogen removal at low temperatures from ammonium-rich wastewater by the bio-electrocoagulation technology in lab-scale systems, pilot-scale systems and a full-scale industrial wastewater treatment plant.

    Science.gov (United States)

    Li, Liang; Qian, Guangsheng; Ye, Linlin; Hu, Xiaomin; Yu, Xin; Lyu, Weijian

    2018-04-17

    In cold areas, nitrogen removal performance of wastewater treatment plants (WWTP) declines greatly in winter. This paper systematically describes the enhancement effect of a periodic reverse electrocoagulation technology on biological nitrogen removal at low temperatures. The study showed that in the lab-scale systems, the electrocoagulation technology improved the biomass amount, enzyme activity and the amount of nitrogen removal bacteria (Nitrosomonas, Nitrobacter, Paracoccus, Thauera and Enterobacter). This enhanced nitrification and denitrification of activated sludge at low temperatures. In the pilot-scale systems, the electrocoagulation technology increased the relative abundance of cold-adapted microorganisms (Luteimonas and Trueperaceae) at low temperatures. In a full-scale industrial WWTP, comparison of data from winter 2015 and winter 2016 showed that effluent chemical oxygen demand (COD), NH 4 + -N, and NO 3 - -N reduced by 10.37, 3.84, and 136.43 t, respectively, throughout the winter, after installation of electrocoagulation devices. These results suggest that the electrocoagulation technology is able to improve the performance of activated sludge under low-temperature conditions. This technology provides a new way for upgrading of the performance of WWTPs in cold areas. Copyright © 2018 Elsevier Ltd. All rights reserved.

  10. PERSPECTIVE IN PLANT DRUG RESEARCH

    Science.gov (United States)

    Singh, R.H.; Singh, K.P.

    1990-01-01

    Plant medicine becomes more popular thought the world in these days probably of its latest toxicity. Ayurveda that leads in plant medicine preserves the natural form of herbs maximum, in various pharmaceutical preparations. Isolation of active principles has not proved much fruitful. However, the need of hour is cultivation of more medicinal plants along with popularization of their use traditional simpler forms. PMID:22557691

  11. Seismic reflection data report: Waste Isolation Pilot Plant (WIPP) site, Southeastern New Mexico

    International Nuclear Information System (INIS)

    Hern, J.L.; Powers, D.W.; Barrows, L.J.

    1978-12-01

    Volume II contains uninterpreted processed lines and shotpoint maps from three seismic reflection surveys conducted from 1976 through 1978 by Sandia Laboratories to support investigations for the Waste Isolation Pilot Plant. Data interpretations will be the subject of subsequent reports

  12. NPDES Permit for Crow Municipal Rural & Industrial Pilot Water Treatment Plant in Montana

    Science.gov (United States)

    Under NPDES permit MT-0031827, the Crow Indian Tribe is authorized to discharge from the Crow Municipal Rural & Industrial (MR&I) Pilot Water Treatment Plant in Bighorn County, Montana to the Bighorn River.

  13. WIPP conceptual design report. Addendum C. Cost worksheets for Waste Isolation Pilot Plant (WIPP)

    International Nuclear Information System (INIS)

    1977-04-01

    The cost worksheets for the Waste Isolation Pilot Plant (WIPP) are presented. A summary cost estimate, cost estimate for surface facilities, and cost estimate for shafts and underground facilities are included

  14. WIPP conceptual design report. Addendum G. Accident analysis for Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    Shefelbine, H.C.; Metcalf, J.H.

    1977-06-01

    The types of accidents or risks pertinent to the Waste Isolation Pilot Plant (WIPP) are presented. Design features addressing these risks are discussed. Also discussed are design features that protect the public

  15. Waste Isolation Pilot Plant No-migration variance petition. Addendum: Volume 7, Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    1990-03-01

    This report describes various aspects of the Waste Isolation Pilot Plant (WIPP) including design data, waste characterization, dissolution features, ground water hydrology, natural resources, monitoring, general geology, and the gas generation/test program.

  16. Mechanical compaction of Waste Isolation Pilot Plant simulated waste

    International Nuclear Information System (INIS)

    Butcher, B.M.; Thompson, T.W.; VanBuskirk, R.G.; Patti, N.C.

    1991-06-01

    The investigation described in this report acquired experimental information about how materials simulating transuranic (TRU) waste compact under axial compressive stress, and used these data to define a model for use in the Waste Isolation Pilot Plant (WIPP) disposal room analyses. The first step was to determine compaction curves for various simultant materials characteristic of TRU waste. Stress-volume compaction curves for various combinations of these materials were than derived to represent the combustible, metallic, and sludge waste categories. Prediction of compaction response in this manner is considered essential for the WIPP program because of the difficulties inherent in working with real (radioactive) waste. Next, full-sized 55-gallon drums of simulated combustible, metallic, and sludge waste were axially compacted. These results provided data that can be directly applied to room consolidation and data for comparison with the predictions obtained in Part 1 of the investigation. Compaction curves, which represent the combustible, metallic, and sludge waste categories, were determined, and a curve for the averaged waste inventory of the entire repository was derived. 9 refs., 31 figs., 12 tabs

  17. The Waste Isolation Pilot Plant Performance Assessment Program

    International Nuclear Information System (INIS)

    Myers, J.; Coons, W.E.; Eastmond, R.; Morse, J.; Chakrabarti, S.; Zurkoff, J.; Colton, I.D.; Banz, I.

    1986-01-01

    The Waste Isolation Pilot Plant (WIPP) Performance Assessment Program involves a comprehensive analysis of the WIPP project with respect to the recently finalized Environmental Protection Agency regulations regarding the long-term geologic isolation of radioactive wastes. The performance assessment brings together the results of site characterization, underground experimental, and environmental studies into a rigorous determination of the performance of WIPP as a disposal system for transuranic radioactive waste. The Program consists of scenario development, geochemical, hydrologic, and thermomechanical support analyses and will address the specific containment and individual protection requirements specified in 40 CFR 191 sub-part B. Calculated releases from these interrelated analyses will be reported as an overall probability distribution of cumulative release resulting from all processes and events occurring over the 10,000 year post-closure period. In addition, results will include any doses to the public resulting from natural processes occurring over the 1,000 year post-closure period. The overall plan for the WIPP Performance Assessment Program is presented along with approaches to issues specific to the WIPP project

  18. Experimental program plan for the Waste Isolation Pilot Plant

    Energy Technology Data Exchange (ETDEWEB)

    1994-01-01

    The US Department of Energy has prepared this Experimental Program Plan for the Waste Isolation Pilot Plant (EPP) to provide a summary of the DOE experimental efforts needed for the performance assessment process for the WIPP, and of the linkages of this process to the appropriate regulations. The Plan encompasses a program of analyses of the performance of the planned repository based on scientific studies, including tests with transuranic waste at laboratory sites, directed at evaluating compliance with the principal regulations governing the WIPP. The Plan begins with background information on the WIPP project, the requirements of the LWA (Land Withdrawal Act), and its objective and scope. It then presents an overview of the regulatory requirements and the compliance approach. Next are comprehensive discussions of plans for compliance with disposal regulations, followed by the SWDA (Solid Waste Disposal Act) and descriptions of activity programs designed to provide information needed for determining compliance. Descriptions and justifications of all currently planned studies designed to support regulatory compliance activities are also included.

  19. Waset Isolation Pilot Plant Annual Site Environmental Report for 2006

    International Nuclear Information System (INIS)

    2007-01-01

    The purpose of the Waste Isolation Pilot Plant Annual Site Environmental Report for 2006 (ASER) is to provide information required by U.S. Department of Energy (DOE) Order 231.1A, Environment, Safety, and Health Reporting. Specifically, the ASER presents summary environmental data that: (a) Characterize site environmental management performance; (b) Summarize environmental occurrences and responses reported during the calendar year; (c) Confirm compliance with environmental standards and requirements; and (d) Highlight significant facility programs and efforts. The DOE Carlsbad Field Office (CBFO) and Washington TRU Solutions LLC (WTS) maintain and preserve the environmental resources at the WIPP site. DOE Order 231.1A; DOE Order 450.1, Environmental Protection Program; and DOE Order 5400.5, Radiation Protection of the Public and Environment, require that the affected environment at and near DOE facilities be monitored to ensure the safety and health of the public and the environment. This report was prepared in accordance with DOE Order 231.1A. This order requires that DOE facilities submit an ASER to the DOE Headquarters Office of the Assistant Secretary for Environment, Safety, and Health. The WIPP Hazardous Waste Facility Permit (HWFP) (No. NM4890139088-TSDF [treatment, storage, and disposal facility]) further requires that the ASER be provided to the New Mexico Environment Department (NMED).

  20. Regulatory basis for the Waste Isolation Pilot Plant performance assessment

    International Nuclear Information System (INIS)

    Howard, Bryan A.; Crawford, M.B.; Galson, D.A.; Marietta, Melvin G.

    2000-01-01

    The Waste Isolation Pilot Plant (WIPP) is the first operational repository designed for the safe disposal of transuranic (TRU) radioactive waste from the defense programs of the US Department of Energy (DOE). The US Environmental Protection Agency (EPA) is responsible for certifications and regulation of the WIPP facility for the radioactive components of the waste. The EPA has promulgated general radioactive waste disposal standards at 40 CFR Part 191. and WIPP-specific criteria to implement and interpret the generic disposal standards at 40 CFR Part 194. In October 1996. the DOE submitted its Compliance Certification Application (CCA) to the EPA to demonstrate compliance with the disposal standards at Subparts B and C of 40 CFR Part 191. This paper summarizes the development of the overall legal framework for radioactive waste disposal at the WIPP, the parallel development of the WIPP performance assessment (PA), and how the EPA disposal standards and implementing criteria formed the basis for the CCA WIPP PA. The CCA resulted in a certification in May 1998 by the EPA of the WIPP'S compliance with the EPA's disposal standard, thus enabling the WIPP to begin radioactive waste disposal

  1. Key Geomechanics Issues at the Waste Isolation Pilot Plant Geomechanics

    International Nuclear Information System (INIS)

    HANSEN, FRANCIS D.

    1999-01-01

    Mechanical and hydrological properties of rock salt provide excellent bases for geological isolation of hazardous materials. Regulatory compliance determinations for the Waste Isolation Pilot Plant (WIPP) stand as testament to the widely held conclusion that salt provides excellent isolation properties. The WIPP saga began in the 1950s when the U.S. National Academy of Sciences (NAS) recommended a salt vault as a promising solution to the national problem of nuclear waste disposal. For over 20 years, the Scientific basis for the NAS recommendation has been fortified by Sandia National Laboratories through a series of large scale field tests and laboratory investigations of salt properties. These scientific investigations helped develop a comprehensive understanding of salt's 4 reformational behavior over an applicable range of stresses and temperatures. Sophisticated constitutive modeling, validated through underground testing, provides the computational ability to model long-term behavior of repository configurations. In concert with advancement of the mechanical models, fluid flow measurements showed not only that the evaporite lithology was essentially impermeable but that the WIPP setting was hydrologically inactive. Favorable mechanical properties ensure isolation of materials placed in a salt geological setting. Key areas of the geomechanics investigations leading to the certification of WIPP are in situ experiments, laboratory tests, and shaft seal design

  2. Summary of scientific investigations for the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    Weart, W.D.

    1996-01-01

    The scientific issues concerning disposal of radioactive wastes in salt formations have received 40 years of attention since the National Academy of Sciences (NAS) first addressed this issue in the mid-50s. For the last 21 years, Sandia National Laboratories (SNL) have directed site specific studies for the Waste Isolation Pilot Plant (WIPP). This paper will focus primarily on the WIPP scientific studies now in their concluding stages, the major scientific controversies regarding the site, and some of the surprises encountered during the course of these scientific investigations. The WIPP project's present understanding of the scientific processes involved continues to support the site as a satisfactory, safe location for the disposal of defense-related transuranic waste and one which will be shown to be in compliance with Environmental Protection Agency (EPA) standards. Compliance will be evaluated by incorporating data from these experiments into Performance Assessment (PA) models developed to describe the physical and chemical processes that could occur at the WIPP during the next 10,000 years under a variety of scenarios. The resulting compliance document is scheduled to be presented to the EPA in October 1996 and all relevant information from scientific studies will be included in this application and the supporting analyses. Studies supporting this compliance application conclude the major period of scientific investigation for the WIPP. Further studies will be of a ''confirmatory'' and monitoring nature

  3. Waset Isolation Pilot Plant Annual Site Environmental Report for 2006

    Energy Technology Data Exchange (ETDEWEB)

    Washington Regulatory and Environmental Services; Washington TRU Solutions LLC

    2007-09-26

    The purpose of the Waste Isolation Pilot Plant Annual Site Environmental Report for 2006 (ASER) is to provide information required by U.S. Department of Energy (DOE) Order 231.1A, Environment, Safety, and Health Reporting. Specifically, the ASER presents summary environmental data that: (a) Characterize site environmental management performance; (b) Summarize environmental occurrences and responses reported during the calendar year; (c) Confirm compliance with environmental standards and requirements; and (d) Highlight significant facility programs and efforts. The DOE Carlsbad Field Office (CBFO) and Washington TRU Solutions LLC (WTS) maintain and preserve the environmental resources at the WIPP site. DOE Order 231.1A; DOE Order 450.1, Environmental Protection Program; and DOE Order 5400.5, Radiation Protection of the Public and Environment, require that the affected environment at and near DOE facilities be monitored to ensure the safety and health of the public and the environment. This report was prepared in accordance with DOE Order 231.1A. This order requires that DOE facilities submit an ASER to the DOE Headquarters Office of the Assistant Secretary for Environment, Safety, and Health. The WIPP Hazardous Waste Facility Permit (HWFP) (No. NM4890139088-TSDF [treatment, storage, and disposal facility]) further requires that the ASER be provided to the New Mexico Environment Department (NMED).

  4. Waste Isolation Pilot Plant: Draft Supplement Environmental Impact Statement

    International Nuclear Information System (INIS)

    1989-04-01

    The US Department of Energy (DOE) has prepared this supplement to the 1980 Final Environmental Impact Statement (FEIS) for the Waste Isolation Pilot Plant (WIPP) in order to assess the environmental impacts that may occur from the continued development of the WIPP as a minced geologic repository for transuranic (TRU) waste. Since the publication of the FEIS in October 1980, new data collected at the WIPP have led to changes in the understanding of the hydrogeologic characteristics of the area and their potential implications for the long-term performance of the WIPP. In addition, there have been changes in the FEIS Proposed Action and new regulatory requirements. This supplement to the FEIS (SEIS) evaluates the environmental consequences of the Proposed Action as modified since 1980 in light of new data and assumptions. The new information pertains mainly to the geologic and hydrologic systems at the WIPP site and their effect on the long-term performance of the WIPP. The SEIS includes new data indicating that: the permeability of the Salado Formation, the geologic formation in which the WIPP underground facilities are located, is lower than previously believed; the moisture content of the Salado Formation and the consequent brine inflow is higher than previously believed; a higher transmissivity zone is present in the Rustler Formation in the southeastern portion of the WIPP site; and ''salt creep'' (convergence) in the repository occurs faster than previously believed. Volume 2 contains 11 appendices

  5. Waste Isolation Pilot Plant Annual Site Environmental Report for 2010

    International Nuclear Information System (INIS)

    2011-01-01

    The purpose of the Waste Isolation Pilot Plant (WIPP) Annual Site Environmental Report for 2010 (ASER) is to provide information required by U.S. Department of Energy (DOE) Order 231.1A, Environment, Safety, and Health Reporting. Specifically, the ASER presents summary environmental data to: (1) Characterize site environmental management performance. (2) Summarize environmental occurrences and responses reported during the calendar year. (3) Confirm compliance with environmental standards and requirements. (4) Highlight significant environmental accomplishments, including progress toward the DOE Environmental Sustainability Goals made through implementation of the WIPP Environmental Management System (EMS). The DOE Carlsbad Field Office (CBFO) and the management and operating contractor (MOC), Washington TRU Solutions LLC (WTS), maintain and preserve the environmental resources at the WIPP. DOE Order 231.1A; DOE Order 450.1A, Environmental Protection Program; and DOE Order 5400.5, Radiation Protection of the Public and the Environment, require that the affected environment at and near DOE facilities be monitored to ensure the safety and health of the public and workers, and preservation of the environment. This report was prepared in accordance with DOE Order 231.1A, which requires that DOE facilities submit an ASER to the DOE Headquarters Chief Health, Safety, and Security Officer. The WIPP Hazardous Waste Facility Permit Number NM4890139088-TSDF (Permit) further requires that the ASER be provided to the New Mexico Environment Department (NMED).

  6. Compliance status report for the Waste Isolation Pilot Plant

    Energy Technology Data Exchange (ETDEWEB)

    1994-03-31

    The US Department of Energy (DOE) is responsible for the disposition of transuranic (TRU) waste generated through national defense-related activities. Approximately 53,700 m{sup 2} of these wastes have been generated and are currently stored at government defense installations across the country. The Waste Isolation Pilot Plant (WIPP), located in southeastern New Mexico, has been sited and constructed to meet the criteria established by the scientific and regulatory community for the safe, long-term disposal of TRU and TRU-mixed wastes. This Compliance Status Report (CSR) provides an assessment of the progress of the WIPP Program toward compliance with long-term disposal regulations, set forth in Title 40 CFR 191 (EPA, 1993a), Subparts B and C, and Title 40 CFR {section}268.6 (EPA, 1993b), in order to focus on-going and future experimental and engineering activities. The CSR attempts to identify issues associated with the performance of the WIPP as a long-term repository and to focus on the resolution of these issues. This report will serve as a tool to focus project resources on the areas necessary to ensure complete, accurate, and timely submittal of the compliance application. This document is not intended to constitute a statement of compliance or a demonstration of compliance.

  7. The waste isolation pilot plant project: a changing paradigm

    International Nuclear Information System (INIS)

    Sheppard, L.E.; McFadden, M.H.

    1996-01-01

    The Waste Isolation Pilot Plant (WIPP) is a US Department of Energy (DOE) repository that has been developed to demonstrate the safe and permanent isolation of transuranic radioactive wastes in a deep geologic site. It is located in 650 m below the surface in a bedded salt formation, and is designed to hold approximately 175,500 cubic meters of waste. Compliance with the regulations has become the principal focus for the Project. The scientific baseline is an important and integral part of the CCA, as it provides the foundation for conducting total system performance assessment calculations for comparison with applicable standards. The activities required to support the scientific baseline are being pursued in parallel to minimize the time required to collect, analyze, interpret and fully incorporate the results into the CCA. The DOE has shifted its approach to demonstrating compliance with the applicable regulations from a paradigm of a series of broad investigations to a new paradigm of highly focused activities conducted in parallel. The success of this approach will be assessed by the EPA when the application is critically reviewed

  8. Waste Isolation Pilot Plant Annual Site Environmental Report for 2010

    Energy Technology Data Exchange (ETDEWEB)

    None

    2011-09-01

    The purpose of the Waste Isolation Pilot Plant (WIPP) Annual Site Environmental Report for 2010 (ASER) is to provide information required by U.S. Department of Energy (DOE) Order 231.1A, Environment, Safety, and Health Reporting. Specifically, the ASER presents summary environmental data to: (1) Characterize site environmental management performance. (2) Summarize environmental occurrences and responses reported during the calendar year. (3) Confirm compliance with environmental standards and requirements. (4) Highlight significant environmental accomplishments, including progress toward the DOE Environmental Sustainability Goals made through implementation of the WIPP Environmental Management System (EMS). The DOE Carlsbad Field Office (CBFO) and the management and operating contractor (MOC), Washington TRU Solutions LLC (WTS), maintain and preserve the environmental resources at the WIPP. DOE Order 231.1A; DOE Order 450.1A, Environmental Protection Program; and DOE Order 5400.5, Radiation Protection of the Public and the Environment, require that the affected environment at and near DOE facilities be monitored to ensure the safety and health of the public and workers, and preservation of the environment. This report was prepared in accordance with DOE Order 231.1A, which requires that DOE facilities submit an ASER to the DOE Headquarters Chief Health, Safety, and Security Officer. The WIPP Hazardous Waste Facility Permit Number NM4890139088-TSDF (Permit) further requires that the ASER be provided to the New Mexico Environment Department (NMED).

  9. Waste acceptance criteria for the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    1996-04-01

    The Waste Isolation Pilot Plant (WIPP) Waste Acceptance Criteria (WAC), DOE/WIPP-069, was initially developed by a U.S. Department of Energy (DOE) Steering Committee to provide performance requirements to ensure public health and safety as well as the safe handling of transuranic (TRU) waste at the WIPP. This revision updates the criteria and requirements of previous revisions and deletes those which were applicable only to the test phase. The criteria and requirements in this document must be met by participating DOE TRU Waste Generator/Storage Sites (Sites) prior to shipping contact-handled (CH) and remote-handled (RH) TRU waste forms to the WIPP. The WIPP Project will comply with applicable federal and state regulations and requirements, including those in Titles 10, 40, and 49 of the Code of Federal Regulations (CFR). The WAC, DOE/WIPP-069, serves as the primary directive for assuring the safe handling, transportation, and disposal of TRU wastes in the WIPP and for the certification of these wastes. The WAC identifies strict requirements that must be met by participating Sites before these TRU wastes may be shipped for disposal in the WIPP facility. These criteria and requirements will be reviewed and revised as appropriate, based on new technical or regulatory requirements. The WAC is a controlled document. Revised/changed pages will be supplied to all holders of controlled copies

  10. Waste Isolation Pilot Plant Biennial Environmental Compliance Report

    International Nuclear Information System (INIS)

    2006-01-01

    This Biennial Environmental Compliance Report (BECR) documents compliance with environmental regulations at the Waste Isolation Pilot Plant (WIPP), a facility designed and authorized for the safe disposal of transuranic (TRU) radioactive waste. This BECR covers the reporting period from April 1, 2004, to March 31, 2006. As required by the WIPP Land Withdrawal Act (LWA) (Public Law [Pub. L.] 102-579, as amended by Pub. L. 104-201), the BECR documents United States (U.S.) Department of Energy (DOE) compliance with regulations and permits issued pursuant to the following: (1) Title 40 Code of Federal Regulations (CFR) Part 191, Subpart A, 'Environmental Standards for Management and Storage'; (2) Clean Air Act (CAA) (42 United States Code [U.S.C.] 7401, et seq.); (3) Solid Waste Disposal Act (SWDA) (42 U.S.C. 6901-6992, et seq.); (4) Safe Drinking Water Act (SDWA) (42 U.S.C. 300f, et seq.); (5) Toxic Substances Control Act (TSCA) (15 U.S.C. 2601, et seq.); (6) Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) (42 U.S.C. 9601, et seq.); and all other federal and state of New Mexico laws pertaining to public health and safety or the environment.

  11. The 1996 performance assessment for the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    Anderson, D.R.; Jow, H.N.; Marietta, M.G.; Chu, M.S.Y.; Shephard, L.E.; Helton, J.C.; Basabilvazo, G.

    1998-01-01

    The Waste Isolation Pilot Plant (WIPP) is under development by the US Department of Energy (DOE) for the geologic disposal of transuranic (TRU) waste that has been generated at government defense installations in the United States. The WIPP is located in an area of low population density in southeastern New Mexico. Waste disposal will take place in excavated chambers in a bedded salt formation approximately 655 m below the land surface. This presentation describes a performance assessment (PA) carried out at Sandia National Laboratories (SNL) to support the Compliance Certification Application (CCA) made by the DOE to the US Environmental Protection Agency (EPA) in October, 1996, for the certification of the WIPP for the disposal of TRU waste. Based on the CCA supported by the PA described in this presentation, the EPA has issued a preliminary decision to certify the WIPP for the disposal of TRU waste. At present (April 1998), it appears likely that the WIPP will be in operation by the end of 1998

  12. Experimental program plan for the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    1994-01-01

    The US Department of Energy has prepared this Experimental Program Plan for the Waste Isolation Pilot Plant (EPP) to provide a summary of the DOE experimental efforts needed for the performance assessment process for the WIPP, and of the linkages of this process to the appropriate regulations. The Plan encompasses a program of analyses of the performance of the planned repository based on scientific studies, including tests with transuranic waste at laboratory sites, directed at evaluating compliance with the principal regulations governing the WIPP. The Plan begins with background information on the WIPP project, the requirements of the LWA (Land Withdrawal Act), and its objective and scope. It then presents an overview of the regulatory requirements and the compliance approach. Next are comprehensive discussions of plans for compliance with disposal regulations, followed by the SWDA (Solid Waste Disposal Act) and descriptions of activity programs designed to provide information needed for determining compliance. Descriptions and justifications of all currently planned studies designed to support regulatory compliance activities are also included

  13. Waste Isolation Pilot Plant Biennial Environmental Compliance Report

    Energy Technology Data Exchange (ETDEWEB)

    Washington Regulatory and Environmental Services

    2006-10-12

    This Biennial Environmental Compliance Report (BECR) documents compliance with environmental regulations at the Waste Isolation Pilot Plant (WIPP), a facility designed and authorized for the safe disposal of transuranic (TRU) radioactive waste. This BECR covers the reporting period from April 1, 2004, to March 31, 2006. As required by the WIPP Land Withdrawal Act (LWA) (Public Law [Pub. L.] 102-579, as amended by Pub. L. 104-201), the BECR documents United States (U.S.) Department of Energy (DOE) compliance with regulations and permits issued pursuant to the following: (1) Title 40 Code of Federal Regulations (CFR) Part 191, Subpart A, "Environmental Standards for Management and Storage"; (2) Clean Air Act (CAA) (42 United States Code [U.S.C.] §7401, et seq.); (3) Solid Waste Disposal Act (SWDA) (42 U.S.C. §§6901-6992, et seq.); (4) Safe Drinking Water Act (SDWA) (42 U.S.C. §§300f, et seq.); (5) Toxic Substances Control Act (TSCA) (15 U.S.C. §§2601, et seq.); (6) Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) (42 U.S.C. §§9601, et seq.); and all other federal and state of New Mexico laws pertaining to public health and safety or the environment.

  14. Pilot research projects for underground disposal of radioactive wastes in the United States of America

    International Nuclear Information System (INIS)

    Stein, R.; Collyer, P.L.

    1984-01-01

    Disposal of commercial radioactive waste in the United States of America in a deep underground formation will ensure permanent isolation from the biosphere with minimal post-closure surveillance and maintenance. The siting, design and development, performance assessment, operation, licensing, certification and decommissioning of an underground repository have stimulated the development of several pilot research projects throughout the country. These pilot tests and projects, along with their resulting data base, are viewed as important steps in the overall location and construction of a repository. Beginning in the 1960s, research at pilot facilities has progressed from underground spent fuel tests in an abandoned salt mine to the production of vitrified nuclear waste in complex borosilicate glass logs. Simulated underground repository experiments have been performed in the dense basalts of Washington State, the volcanic tuffaceous rock of Nevada and both domal and bedded salts of Louisiana and Kansas. In addition to underground pilot in situ tests, other facilities have been constructed or modified to monitor the performance of spent fuel in dry storage wells and self-shielded concrete casks. As the National Waste Terminal Storage (NWTS) programme advances to the next stage of underground site characterization for each of three different geological sites, additional pilot facilities are under consideration. These include a Test and Evaluation Facility (TEF) for site verification and equipment performance and testing, as well as a salt testing facility for verification of in situ simulation equipment. Although not associated with the NWTS programme, the construction of the Waste Isolation Pilot Plant (WIPP) in the bedded salts of New Mexico is well under way for deep testing and experimentation with the defence programme's transuranic nuclear waste. (author)

  15. AD-1 with research pilot Richard E. Gray

    Science.gov (United States)

    1982-01-01

    Standing in front of the AD-1 Oblique Wing research aircraft is research pilot Richard E. Gray. Richard E. Gray joined National Aeronautics and Space Administration's Johnson Space Center, Houston, Texas, in November 1978, as an aerospace research pilot. In November 1981, Dick joined the NASA's Ames-Dryden Flight Research Facility, Edwards, California, as a research pilot. Dick was a former Co-op at the NASA Flight Research Center (a previous name of the Ames-Dryden Flight Research Facility), serving as an Operations Engineer. At Ames-Dryden, Dick was a pilot for the F-14 Aileron Rudder Interconnect Program, AD-1 Oblique Wing Research Aircraft, F-8 Digital Fly-By-Wire and Pilot Induced Oscillations investigations. He also flew the F-104, T-37, and the F-15. On November 8, 1982, Gray was fatally injured in a T-37 jet aircraft while making a pilot proficiency flight. Dick graduated with a Bachelors degree in Aeronautical Engineering from San Jose State University in 1969. He joined the U.S. Navy in July 1969, becoming a Naval Aviator in January 1971, when he was assigned to F-4 Phantoms at Naval Air Station (NAS) Miramar, California. In 1972, he flew 48 combat missions in Vietnam in F-4s with VF-111 aboard the USS Coral Sea. After making a second cruise in 1973, Dick was assigned to Air Test and Evaluation Squadron Four (VX-4) at NAS Point Mugu, California, as a project pilot on various operational test and evaluation programs. In November 1978, Dick retired from the Navy and joined NASA's Johnson Space Center. At JSC Gray served as chief project pilot on the WB-57F high-altitude research projects and as the prime television chase pilot in a T-38 for the landing portion of the Space Shuttle orbital flight tests. Dick had over 3,000 hours in more than 30 types of aircraft, an airline transport rating, and 252 carrier arrested landings. He was a member of the Society of Experimental Test Pilots serving on the Board of Directors as Southwest Section Technical Adviser in

  16. Final Report: RPP-WTP Semi-Integrated Pilot Plant

    Energy Technology Data Exchange (ETDEWEB)

    Duignan, M. R.; Adamson, D. J.; Calloway, T. B.; Fowley, M. D.; Qureshi, Z. H.; Steimke, J. L.; Williams, M. R.; Zamecnik, J. R.

    2005-06-01

    In August 2004 the last of the SIPP task testing ended--a task that formally began with the issuance of the RPP-WTP Test Specification in June 2003. The planning for the task was a major effort in itself and culminated with the input of all stakeholders, DOE, Bechtel National, Inc., Washington Group International, in October 2003 at Hanford, WA (Appendix A). This report documents the activities carried out as a result of that planning. Campaign IV, the fourth and final step towards the Semi-Integrated Pilot Plant (SIPP) task, conducted by the Savannah River National Laboratory (SRNL) at the Savannah River Site, was to take the several recycle streams produced in Campaign III, the third step of the task, and combine them with other simulated recycle and chosen waste streams. (Campaign III was fed recycles from Campaign II, as Campaign II was fed by Campaign I.) The combined stream was processed in a fashion that mimicked the pretreatment operations of the DOE River Protection Project--Waste Treatment and Immobilization Plant (RPP-WTP) with the exception of the Ion Exchange Process. The SIPP task is considered semi-integrated because it only deals with the pretreatment operations of the RPP-WTP. That is, the pilot plant starts by receiving waste from the tank farm and ends when waste is processed to the point of being sent for vitrification. The resulting pretreated LAW and HLW simulants produced by the SIPP were shipped to VSL (Vitreous State Laboratory) and successfully vitrified in pilot WTP melters. Within the SIPP task these steps are referred to as Campaigns and there were four Campaigns in all. Campaign I, which is completely different than other campaigns, subjected a simulant of Hanford Tank 241-AY-102/C-106 (AY102) waste to cross-flow ultrafiltration only and in that process several important recycle streams were produced as a result of washing the simulant and cleaning the cross-flow filter. These streams were fed to subsequent campaigns and that work was

  17. Final Report: RPP-WTP Semi-Integrated Pilot Plant

    International Nuclear Information System (INIS)

    Duignan, M. R.; Adamson, D. J.; Calloway, T. B.; Fowley, M. D.; Qureshi, Z. H.; Steimke, J. L.; Williams, M. R.; Zamecnik, J. R.

    2005-01-01

    In August 2004 the last of the SIPP task testing ended--a task that formally began with the issuance of the RPP-WTP Test Specification in June 2003. The planning for the task was a major effort in itself and culminated with the input of all stakeholders, DOE, Bechtel National, Inc., Washington Group International, in October 2003 at Hanford, WA (Appendix A). This report documents the activities carried out as a result of that planning. Campaign IV, the fourth and final step towards the Semi-Integrated Pilot Plant (SIPP) task, conducted by the Savannah River National Laboratory (SRNL) at the Savannah River Site, was to take the several recycle streams produced in Campaign III, the third step of the task, and combine them with other simulated recycle and chosen waste streams. (Campaign III was fed recycles from Campaign II, as Campaign II was fed by Campaign I.) The combined stream was processed in a fashion that mimicked the pretreatment operations of the DOE River Protection Project--Waste Treatment and Immobilization Plant (RPP-WTP) with the exception of the Ion Exchange Process. The SIPP task is considered semi-integrated because it only deals with the pretreatment operations of the RPP-WTP. That is, the pilot plant starts by receiving waste from the tank farm and ends when waste is processed to the point of being sent for vitrification. The resulting pretreated LAW and HLW simulants produced by the SIPP were shipped to VSL (Vitreous State Laboratory) and successfully vitrified in pilot WTP melters. Within the SIPP task these steps are referred to as Campaigns and there were four Campaigns in all. Campaign I, which is completely different than other campaigns, subjected a simulant of Hanford Tank 241-AY-102/C-106 (AY102) waste to cross-flow ultrafiltration only and in that process several important recycle streams were produced as a result of washing the simulant and cleaning the cross-flow filter. These streams were fed to subsequent campaigns and that work was

  18. Solvent Refined Coal (SRC) process: trace elements. Research and development report No. 53, interim report No. 30. Volume III. Pilot plant development work. Part 6. The fate of trace elements in the SRC process

    International Nuclear Information System (INIS)

    Khalil, S.R.

    1980-02-01

    Instrumental neutron activation analysis was used to study the distribution and fate of up to 36 elements in the Solvent Refined Coal Process Pilot Plant located at Fort Lewis, Washington. The elements Ti, V, Mg, Ca, Al, Cl, Mn, As, Br, Na, K, Sm, La, Ga, Cu, Sb, Se, Hg, Ni, Co, Cr, Fe, Rb, Cs, Sc, Tb, Eu, Ce, Sr, Ba, Th, U, Hf, Ta, Zr and Zn were measured in feed coal, insoluble residues, process solvent, process and effluent waters, by-product sulfur, SRC-I solid product, liquid-liquid separator oils and SRC-II liquid products. The material balance was calculated for each element from the concentration data and yields of each process fraction for both the SRC-I and SRC-II processes. Except for Ti, Cl and Br in the SRC-I mode and Hg in the SRC-II mode, each element was substantially lower in the SRC products than in the original feed coal. Residues from the process contained more than 80% of the trace element content found in the coal, except for Hg. More than 98.5% of the total contents of K and Fe in coal were retained in the insoluble residues. Elements such as Hg, Se, As and Sb can form volatile compounds (such as Hg 0 , H 2 Se, AsH 3 and SbH 3 ) stable under the process conditions. The high enhancement factors of Se (957), As (202) and Sb (27.4) in the aqueous phase of the separator water compared to that of the oil are evidence for the formation of volatile species which are more soluble in water than in the oil phase

  19. Draft Title 40 CFR 191 compliance certification application for the Waste Isolation Pilot Plant. Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-03-31

    The Waste Isolation Pilot Plant (WIPP) is a research and development facility for the demonstration of the permanent isolation of transuranic radioactive wastes in a geologic formation. The facility was constructed in southeastern New Mexico in a manner intended to meet criteria established by the scientific and regulatory community for the safe, long-term disposal of transuranic wastes. The US Department of Energy (DOE) is preparing an application to demonstrate compliance with the requirements outlined in Title 40, Part 191 of the Code of Federal Regulations (CFR) for the permanent disposal of transuranic wastes. As mandated by the Waste Isolation Pilot Plant (WIPP) Land Withdrawal Act of 1992, the US Environmental Protection Agency (EPA) must evaluate this compliance application and provide a determination regarding compliance with the requirements within one year of receiving a complete application. Because the WIPP is a very complex program, the DOE has planned to submit the application as a draft in two parts. This strategy will allow for the DOE and the EPA to begin technical discussions on critical WIPP issues before the one-year compliance determination period begins. This report is the first of these two draft submittals.

  20. Draft Title 40 CFR 191 compliance certification application for the Waste Isolation Pilot Plant. Volume 1

    International Nuclear Information System (INIS)

    1995-01-01

    The Waste Isolation Pilot Plant (WIPP) is a research and development facility for the demonstration of the permanent isolation of transuranic radioactive wastes in a geologic formation. The facility was constructed in southeastern New Mexico in a manner intended to meet criteria established by the scientific and regulatory community for the safe, long-term disposal of transuranic wastes. The US Department of Energy (DOE) is preparing an application to demonstrate compliance with the requirements outlined in Title 40, Part 191 of the Code of Federal Regulations (CFR) for the permanent disposal of transuranic wastes. As mandated by the Waste Isolation Pilot Plant (WIPP) Land Withdrawal Act of 1992, the US Environmental Protection Agency (EPA) must evaluate this compliance application and provide a determination regarding compliance with the requirements within one year of receiving a complete application. Because the WIPP is a very complex program, the DOE has planned to submit the application as a draft in two parts. This strategy will allow for the DOE and the EPA to begin technical discussions on critical WIPP issues before the one-year compliance determination period begins. This report is the first of these two draft submittals

  1. A soil washing pilot plant for removing petroleum hydrocarbons from contaminated soils

    International Nuclear Information System (INIS)

    Toor, I.A.; Roehrig, G.R.

    1992-01-01

    A soil washing pilot plant was built and tested for its ability to remove petroleum hydrocarbons from certain soils. The ITEX soil washing pilot plant is a trailer mountable mobile unit which has a washing capacity of two tons per hour of contaminated soils. A benchscale study was carried out prior to the fabrication of the pilot plant. The first sample was contaminated with diesel fuel while the second sample was contaminated with crude oil. Various nonionic, cationic and anionic cleaning agents were evaluated for their ability to remove petroleum hydrocarbons from these materials. The nonionic cleaning agents were more successful in cleaning the soils in general. The ultimate surfactant choice was based on several factors including cost, biodegradability, cleaning efficiency and other technical considerations. The soil samples were characterized in terms of their particle size distributions. Commercial diesel fuel was carefully mixed in this sand to prepare a representative sample for the pilot plant study. Two pilot runs were made using this material. A multistage washing study was also conducted in the laboratory which indicates that the contamination level can be reduced to 100 ppm using only four stages. Because the pilot plant washing efficiency is twice as high, it is believed that ultimate contamination levels can be reduced to lower levels using the same number of stages. However, this hypothesis has not been demonstrated to date

  2. Achievement report for fiscal 1993 on developing entrained bed coal gasification power plant. Part 4. Pilot plant operation edition; 1993 nendo seika hokokusho. Funryusho sekitan gaska hatsuden plant kaihatsu - Sono 4. Pilot plant unten sosa hen

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-02-01

    Tests and researches have been carried out on operation of a 200-t/d entrained bed coal gasification pilot plant built with an objective of establishing the coal gasification composite power generation technology. This paper summarizes the operation achievements in fiscal 1993. The plant operation record in fiscal 1993 was as follows: 430 hours 27 minutes in the gasification furnace (ten gasification operations), 233 hours 51 minutes in the gas refining facility, 140 hours 31 minutes in the gas turbine facility (power generation amount of 746.8 MWh with nine actuations), 1,263 hours 09 minutes in the processing furnace in the safety environment facility, and 427 hours 22 minutes in the NOx removal equipment. Descriptions were given with detailed graphs on the actuation and shutdown record with respect to the run D2, the run D3 (1 and 2), the run D4, the run D5, the run D6, and the run D7 (1 through 4). The operation procedures were prepared for the plant startup and shutdown schedule, the generalization report, the gasification furnace facility, the gas refining facility (dry type desulfurizing facility), the gas refining facility (dry type dust removing facility), the gas turbine facility, the combustor testing facility with actual pressure and size, and the safety environment facilities. (NEDO)

  3. Selective absorption pilot plant for decontamination of fuel reprocessing plant off-gas

    Energy Technology Data Exchange (ETDEWEB)

    Stephenson, M.J.; Eby, R.S.; Huffstetler, V.C.

    1977-10-01

    A fluorocarbon-based selective absorption process for removing krypton-85, carbon-14, and radon-222 from the off-gas of conventional light water and advanced reactor fuel reprocessing plants is being developed at the Oak Ridge Gaseous Diffusion Plant in conjunction with fuel recycle work at the Oak Ridge National Laboratory and at the Savannah River Laboratory. The process is characterized by an especially high tolerance for many other reprocessing plant off-gas components. This report presents detailed drawings and descriptions of the second generation development pilot plant as it has evolved after three years of operation. The test facility is designed on the basis of removing 99% of the feed gas krypton and 99.9% of the carbon and radon, and can handle a nominal 15 scfm (425 slm) of contaminated gas at pressures from 100 to 600 psig (7.0 to 42.2 kg/cm/sup 2/) and temperatures from minus 45 to plus 25/sup 0/F (-43 to -4/sup 0/C). Part of the development program is devoted to identifying flowsheet options and simplifications that lead to an even more economical and reliable process. Two of these applicative flowsheets are discussed.

  4. Final environmental impact statement. Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    1980-10-01

    In accordance with the National Environmental Policy Act (NEPA) of 1969, the US Department of Energy (DOE) has prepared this document as environmental input to future decisions regarding the Waste Isolation Pilot Plant (WIPP), which would include the disposal of transuranic waste, as currently authorized. The alternatives covered in this document are the following: (1) Continue storing transuranic (TRU) waste at the Idaho National Engineering Laboratory (INEL) as it is now or with improved confinement. (2) Proceed with WIPP at the Los Medanos site in southeastern New Mexico, as currently authorized. (3) Dispose of TRU waste in the first available repository for high-level waste. The Los Medanos site would be investigated for its potential suitability as a candidate site. This is administration policy and is the alternative preferred by the DOE. (4) Delay the WIPP to allow other candidate sites to be evaluated for TRU-waste disposal. This environmental impact statement is arranged in the following manner: Chapter 1 is an overall summary of the analysis contained in the document. Chapters 2 and 4 set forth the objectives of the national waste-management program and analyze the full spectrum of reasonable alternatives for meeting these objectives, including the WIPP. Chapter 5 presents the interim waste-acceptance criteria and waste-form alternatives for the WIPP. Chapters 6 through 13 provide a detailed description and environmental analysis of the WIPP repository and its site. Chapter 14 describes the permits and approvals necessary for the WIPP and the interactions that have taken place with Federal, State, and local authorities, and with the general public in connection with the repository. Chapter 15 analyzes the many comments received on the DEIS and tells what has been done in this FEIS in response. The appendices contain data and discussions in support of the material in the text

  5. Waste Isolation Pilot Plant Groundwater Protection Management Program Plan

    Energy Technology Data Exchange (ETDEWEB)

    Washington Regulatory and Environmental Services

    2005-07-01

    The DOE established the Groundwater Monitoring Program (GMP) (WP 02-1) to monitor groundwater resources at WIPP. In the past, the GMP was conducted to establish background data of existing conditions of groundwater quality and quantity in the WIPP vicinity, and to develop and maintain a water quality database as required by regulation. Today the GMP is conducted consistent with 204.1.500 NMAC (New MexicoAdministrative Code), "Adoption of 40 CFR [Code of Federal Regulations] Part 264,"specifically 40 CFR §264.90 through §264.101. These sections of 20.4.1 NMAC provide guidance for detection monitoring of groundwater that is, or could be, affected by waste management activities at WIPP. Detection monitoring at WIPP is designed to detect contaminants in the groundwater long before the general population is exposed. Early detection will allow cleanup efforts to be accomplished before any exposure to the general population can occur. Title 40 CFR Part 264, Subpart F, stipulates minimum requirements of Resource Conservation and Recovery Act of 1976 (42 United States Code [U.S.C.] §6901 et seq.) (RCRA) groundwater monitoring programs including the number and location of monitoring wells; sampling and reporting schedules; analytical methods and accuracy requirements; monitoring parameters; and statistical treatment of monitoring data. This document outlines how WIPP intends to protect and preserve groundwater within the WIPP Land Withdrawal Area (WLWA). Groundwater protection is just one aspect of the WIPP environmental protection effort. An overview of the entire environmental protection effort can be found in DOE/WIPP 99-2194, Waste Isolation Pilot Plant Environmental Monitoring Plan. The WIPP GMP is designed to statistically determine if any changes are occurring in groundwater characteristics within and surrounding the WIPP facility. If a change is noted, the cause will then be determined and the appropriate corrective action(s) initiated.

  6. Waste Isolation Pilot Plant Groundwater Protection Management Program Plan

    International Nuclear Information System (INIS)

    2005-01-01

    The DOE established the Groundwater Monitoring Program (GMP) (WP 02-1) to monitor groundwater resources at WIPP. In the past, the GMP was conducted to establish background data of existing conditions of groundwater quality and quantity in the WIPP vicinity, and to develop and maintain a water quality database as required by regulation. Today the GMP is conducted consistent with 204.1.500 NMAC (New Mexico Administrative Code), 'Adoption of 40 CFR [Code of Federal Regulations] Part 264,'specifically 40 CFR 264.90 through 264.101. These sections of 20.4.1 NMAC provide guidance for detection monitoring of groundwater that is, or could be, affected by waste management activities at WIPP. Detection monitoring at WIPP is designed to detect contaminants in the groundwater long before the general population is exposed. Early detection will allow cleanup efforts to be accomplished before any exposure to the general population can occur. Title 40 CFR Part 264, Subpart F, stipulates minimum requirements of Resource Conservation and Recovery Act of 1976 (42 United States Code [U.S.C.] 6901 et seq.) (RCRA) groundwater monitoring programs including the number and location of monitoring wells; sampling and reporting schedules; analytical methods and accuracy requirements; monitoring parameters; and statistical treatment of monitoring data. This document outlines how WIPP intends to protect and preserve groundwater within the WIPP Land Withdrawal Area (WLWA). Groundwater protection is just one aspect of the WIPP environmental protection effort. An overview of the entire environmental protection effort can be found in DOE/WIPP 99-2194, Waste Isolation Pilot Plant Environmental Monitoring Plan. The WIPP GMP is designed to statistically determine if any changes are occurring in groundwater characteristics within and surrounding the WIPP facility. If a change is noted, the cause will then be determined and the appropriate corrective action(s) initiated.

  7. Waste retrieval plan for the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    1993-03-01

    The US DOE has prepared this plan to meet the requirements of Public Law 102579, the Waste Isolation Pilot Plant (WIPP) LWA, The purpose. is to demonstrate readiness to retrieve from the WIPP underground transuranic radioactive waste that will be used for testing should retrieval be needed. The WIPP, a potential geologic repository for transuranic wastes generated in national-defense activities, has been constructed in southeastern New Mexico. Because the transuranic wastes will remain radioactive for a very long time, the WIPP must reasonably ensure safe performance over thousands of years. The DOE therefore decided to develop the facility in phases, to preclude premature decisions and to conduct the performance assessments needed to demonstrate long-term safety. Surface facilities for receiving waste have been built, and considerable underground excavation, 2150 feet below the surface, has been completed. The next step is a test phase, including underground experiments called ''bin tests'' and ''alcove test(s)'' with contact-handled transuranic waste. The objective of these waste tests is to collect relevant data about the gas-generation potential and volatile organic compound (VOC) source term of the waste for developing a basis for demonstrating long term safety by compliance with the applicable disposal regulations (40 CFR 191, 264 and 268). The test phase will end when a decision is made to begin disposal in the WIPP or to terminate the project if regulatory compliance cannot be determined and demonstrated. Authorization to receive transuranic waste at the WIPP for the test phase is given by the WIPP LWA provided certain requirements are met

  8. Waste Isolation Pilot Plant Biennial Environmental Compliance Report

    Energy Technology Data Exchange (ETDEWEB)

    Washinton TRU Solutions LLC

    2002-09-30

    This Biennial Environmental Compliance Report (BECR) documents environmental regulatory compliance at the Waste Isolation Pilot Plant (WIPP), a facility designed for the safe disposal of transuranic (TRU) radioactive waste, for the reporting period of April 1, 2000, to March 31, 2002. As required by the WIPP Land Withdrawal Act (LWA)(Public Law [Pub. L.] 102-579, as amended by Pub. L. 104-201), the BECR documents U.S. Department of Energy (DOE) Carlsbad Field Office's (CBFO) compliance with applicable environmental protection laws and regulations implemented by agencies of the federal government and the state of New Mexico. In the prior BECR, the CBFO and the management and operating contractor (MOC)committed to discuss resolution of a Letter of Violation that had been issued by the New Mexico Environment Department (NMED) in August 1999, which was during the previous BECR reporting period. This Letter of Violation alleged noncompliance with hazardous waste aisle spacing, labeling, a nd tank requirements. At the time of publication of the prior BECR, resolution of the Letter of Violation was pending. On July 7, 2000, the NMED issued a letter noting that the aisle spacing and labeling concerns had been adequately addressed and that they were rescinding the violation alleging that the Exhaust Shaft Catch Basin failed to comply with the requirements for a hazardous waste tank. During the current reporting period, WIPP received a Notice of Violation and a compliance order alleging the violation of the New Mexico Hazardous Waste Regulations and the WIPP Hazardous Waste Facility Permit (HWFP).

  9. Final environmental impact statement. Waste Isolation Pilot Plant

    Energy Technology Data Exchange (ETDEWEB)

    1980-10-01

    In accordance with the National Environmental Policy Act (NEPA) of 1969, the US Department of Energy (DOE) has prepared this document as environmental input to future decisions regarding the Waste Isolation Pilot Plant (WIPP), which would include the disposal of transuranic waste, as currently authorized. The alternatives covered in this document are the following: (1) Continue storing transuranic (TRU) waste at the Idaho National Engineering Laboratory (INEL) as it is now or with improved confinement. (2) Proceed with WIPP at the Los Medanos site in southeastern New Mexico, as currently authorized. (3) Dispose of TRU waste in the first available repository for high-level waste. The Los Medanos site would be investigated for its potential suitability as a candidate site. This is administration policy and is the alternative preferred by the DOE. (4) Delay the WIPP to allow other candidate sites to be evaluated for TRU-waste disposal. This environmental impact statement is arranged in the following manner: Chapter 1 is an overall summary of the analysis contained in the document. Chapters 2 and 4 set forth the objectives of the national waste-management program and analyze the full spectrum of reasonable alternatives for meeting these objectives, including the WIPP. Chapter 5 presents the interim waste-acceptance criteria and waste-form alternatives for the WIPP. Chapters 6 through 13 provide a detailed description and environmental analysis of the WIPP repository and its site. Chapter 14 describes the permits and approvals necessary for the WIPP and the interactions that have taken place with Federal, State, and local authorities, and with the general public in connection with the repository. Chapter 15 analyzes the many comments received on the DEIS and tells what has been done in this FEIS in response. The appendices contain data and discussions in support of the material in the text.

  10. Waste Isolation Pilot Plant Biennial Environmental Compliance Report

    International Nuclear Information System (INIS)

    Washinton TRU Solutions LLC

    2002-01-01

    This Biennial Environmental Compliance Report (BECR) documents environmental regulatory compliance at the Waste Isolation Pilot Plant (WIPP), a facility designed for the safe disposal of transuranic (TRU) radioactive waste, for the reporting period of April 1, 2000, to March 31, 2002. As required by the WIPP Land Withdrawal Act (LWA)(Public Law [Pub. L.] 102-579, as amended by Pub. L. 104-201), the BECR documents U.S. Department of Energy (DOE) Carlsbad Field Office's (CBFO) compliance with applicable environmental protection laws and regulations implemented by agencies of the federal government and the state of New Mexico. In the prior BECR, the CBFO and the management and operating contractor (MOC)committed to discuss resolution of a Letter of Violation that had been issued by the New Mexico Environment Department (NMED) in August 1999, which was during the previous BECR reporting period. This Letter of Violation alleged noncompliance with hazardous waste aisle spacing, labeling, a nd tank requirements. At the time of publication of the prior BECR, resolution of the Letter of Violation was pending. On July 7, 2000, the NMED issued a letter noting that the aisle spacing and labeling concerns had been adequately addressed and that they were rescinding the violation alleging that the Exhaust Shaft Catch Basin failed to comply with the requirements for a hazardous waste tank. During the current reporting period, WIPP received a Notice of Violation and a compliance order alleging the violation of the New Mexico Hazardous Waste Regulations and the WIPP Hazardous Waste Facility Permit (HWFP)

  11. The 10 MWe Solar Thermal Central Receiver Pilot Plant: Solar facilities design integration. Pilot-plant station manual (RADL Item 2-1). Volume 1: System description

    Science.gov (United States)

    1982-09-01

    The complete Barstow Solar Pilot Plant is described. The plant requirements and general description are presented, the mechanical, electric power, and control and instrumentation systems as well as civil engineering and structural aspects and the station buildings are described. Included in the mechanical systems are the heliostats, receiver, thermal storage system, beam characterization system, steam, water, nitrogen, and compressed air systems, chemical feed system, fire protection system, drains, sumps and the waste disposal systems, and heating, ventilating, and air conditioning systems.

  12. Solar pilot plant, phase I. Quarterly report No. 1, July--December 1975

    Energy Technology Data Exchange (ETDEWEB)

    None

    1976-02-20

    Honeywell Inc. is investigating the technical and economic feasibility of generating electricity from solar energy. During the first 6 months of the program (1 July--31 December 1975), a preliminary design baseline for a 10-MW(e) solar pilot plant was generated and analyzed. Subsequently, several changes were made to improve performance and/or reduce cost. Conceptual designs and research experiments were generated for three key subsystems--collector, steam generator, and thermal storage. Limited testing was done to study the problem of removing eutectic salts from vaporizer tubes in the thermal storage subsystem. The program was on schedule at the end of 1975. Plans for the first quarter of 1976 include ordering long-leadtime items for the subsystem research experiments, continuing analysis of the conceptual designs preparatory to detailing them, and continuing engineering model experiments.

  13. Radioactive waste disposal: Waste Isolation Pilot Plants (WIPP). March 1978-November 1989 (Citations from the NTIS data base). Report for Mar 78-Nov 89

    International Nuclear Information System (INIS)

    1990-01-01

    This bibliography contains citations concerning the Waste Isolation Pilot Plant (WIPP), a geologic repository located in New Mexico for transuranic wastes generated by the U.S. Government. Articles follow the development of the program from initial site selection and characterization through construction and testing, along with research programs on environmental impacts, structural design, and radionuclide landfill gases. Existing plants and facilities, pilot plants, migration, rock mechanics, economics, regulations, and transport of wastes to the site are also included. The Salt Repository Project and the Crystalline Repository Project are referenced in related published bibliographies. (Contains 184 citations fully indexed and including a title list.)

  14. MSU-DOE Plant Research Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    1991-01-01

    This document is the compiled progress reports of research funded through the Michigan State University/Department of Energy Plant Research Laboratory. Fourteen reports are included, covering the molecular basis of plant/microbe symbiosis, cell wall biosynthesis and proteins, gene expression, stress responses, plant hormone biosynthesis, interactions between the nuclear and organelle genomes, sensory transduction and tropisms, intracellular sorting and trafficking, regulation of lipid metabolism, molecular basis of disease resistance and plant pathogenesis, developmental biology of Cyanobacteria, and hormonal involvement in environmental control of plant growth. 320 refs., 26 figs., 3 tabs. (MHB)

  15. Plant Research Department annual report 2001

    DEFF Research Database (Denmark)

    Kossmann, J.; Gissel Nielsen, G.; Jakobsen, Iver

    2002-01-01

    of plants to resist fungal attack, and to optimise flowering time. Two programmes are devoted to improving the market value of plant products. Plants withenhanced nutritional value, or that contain novel renewable resources, are designed to add value to the European Agro-Industries. A sixth programme......The Plant Research Department integrates modern post-genomic tools to improve our understanding of plants. The aim is to develop crops with improved agronomic traits and to engineer high-value plants, which are able to meet the growth conditions of thefuture environment. The department is divided...... into six research programmes that are linked through their individual expertise delivered to the rest of the department. Three programmes are engaged in improving the agronomic performance of plants. Genetictools are being developed to enhance the nutrient efficiency of plants, to strengthen the ability...

  16. Biofuels 2.0 move to pilot plant

    International Nuclear Information System (INIS)

    Dupin, L.

    2010-01-01

    The second generation of biofuels, which use the non-energy parts of plants, do not compete with the food industry. These biofuels have been tried and tested at the laboratory but challenges are occurring with the transition to industrial plants. Demonstrators and prototypes are developing in Germany, Japan, USA and France and bet on two different processes, the biochemical way (enzymatic reaction and fermentation) and the thermochemical way (gasification and Fischer-Tropsch synthesis). Research is in progress on a possible third generation of biofuels which will use micro-algae. The interest of this third way is triple: no competition with the food industry, no land use (production in bioreactors), and enhanced CO 2 capture. (J.S.)

  17. Waste Isolation Pilot Plant simulated RH TRU waste experiments: Data and interpretation pilot

    International Nuclear Information System (INIS)

    Molecke, M.A.; Argueello, G.J.; Beraun, R.

    1993-04-01

    The simulated, i.e., nonradioactive remote-handled transuranic waste (RH TRU) experiments being conducted underground in the Waste Isolation Pilot Plant (WIPP) were emplaced in mid-1986 and have been in heated test operation since 9/23/86. These experiments involve the in situ, waste package performance testing of eight full-size, reference RH TRU containers emplaced in horizontal, unlined test holes in the rock salt ribs (walls) of WIPP Room T. All of the test containers have internal electrical heaters; four of the test emplacements were filled with bentonite and silica sand backfill materials. We designed test conditions to be ''near-reference'' with respect to anticipated thermal outputs of RH TRU canisters and their geometrical spacing or layout in WIPP repository rooms, with RH TRU waste reference conditions current as of the start date of this test program. We also conducted some thermal overtest evaluations. This paper provides a: detailed test overview; comprehensive data update for the first 5 years of test operations; summary of experiment observations; initial data interpretations; and, several status; experimental objectives -- how these tests support WIPP TRU waste acceptance, performance assessment studies, underground operations, and the overall WIPP mission; and, in situ performance evaluations of RH TRU waste package materials plus design details and options. We provide instrument data and results for in situ waste container and borehole temperatures, pressures exerted on test containers through the backfill materials, and vertical and horizontal borehole-closure measurements and rates. The effects of heat on borehole closure, fracturing, and near-field materials (metals, backfills, rock salt, and intruding brine) interactions were closely monitored and are summarized, as are assorted test observations. Predictive 3-dimensional thermal and structural modeling studies of borehole and room closures and temperature fields were also performed

  18. Summary of uranium refining and conversion pilot plant at Ningyo-toge works

    International Nuclear Information System (INIS)

    Iwata, Ichiro

    1981-01-01

    In the Ningyo-toge works, Power Reactor and Nuclear Fuel Development Corp., the construction of the uranium refining and conversion pilot plant was completed, and the operation will be started after the various tests based on the related laws. As for the uranium refining in Japan, the PNC process by wet refining method has been developed since 1958. The history of the development is described. It was decided to construct the refining and conversion pilot plant with 200 t uranium/year capacity as the comprehensive result of the development. This is the amount sufficient to supply UF 6 to the uranium enrichment pilot plant in Ningyo-toge. The building for the refining and conversion pilot plant is a three-story ferro-concrete building with the total floor area of about 13,000 m 2 . The raw materials are the uranium ore produced in Ningyo-toge and the yellow cakes from abroad. Uranyl sulfate solution is obtained by solvent extraction using an extraction tower or a mixer-settler. The following processes are electrolytic reduction, precipitation of uranium tetrafluoride, filtration, drying, dehydration and UF 6 conversion. The fluorine for UF 6 conversion is produced by the facility in the plant. The operation of the pilot plant will be started in the latter half of the fiscal year 1981, the batch operation is carrried out in 1982, and the continuous operation from 1983. (Kako, I.)

  19. The design of a continuous ion-exchange pilot plant for the recovery of uranium from partially clarified solutions

    International Nuclear Information System (INIS)

    Cloete, F.L.D.

    1980-01-01

    A preliminary design is given for a pilot plant to recover uranium from partially clarified slime pulp by continuous ion exchange. Process and plant-design methods are indicated briefly, and an outline is given of experimental work that should be undertaken before the start-up of the pilot plant

  20. General Atomic reprocessing pilot plant: description and results of initial testing

    International Nuclear Information System (INIS)

    1977-12-01

    In June 1976 General Atomic completed the construction of a reprocessing head-end cold pilot plant. In the year since then, each system within the head end has been used for experiments which have qualified the designs. This report describes the equipment in the plant and summarizes the results of the initial phase of reprocessing testing

  1. Vitrification of plutonium at Rocky Flats the argument for a pilot plant

    Energy Technology Data Exchange (ETDEWEB)

    Moore, L. [Rocky Mountain Peace Center, Boulder, CO (United States)

    1996-05-01

    Current plans for stabilizing and storing the plutonium at Rocky Flats Plant fail to put the material in a form suitable for disposition and resistant to proliferation. Vitrification should be considered as an alternate technology. The vitrification should begin with a small-scale pilot plant.

  2. Performance and Model Calibration of R-D-N Processes in Pilot Plant

    DEFF Research Database (Denmark)

    de la Sota, A.; Larrea, L.; Novak, L.

    1994-01-01

    This paper deals with the first part of an experimental programme in a pilot plant configured for advanced biological nutrient removal processes treating domestic wastewater of Bilbao. The IAWPRC Model No.1 was calibrated in order to optimize the design of the full-scale plant. In this first phas...

  3. Dismantling of an alpha contaminated hot cell at the Marcoule Pilot Plant

    International Nuclear Information System (INIS)

    Tachon, M.

    1988-01-01

    For the remodeling of Marcoule Pilot Plant, the cell 82: old unit for plutonium solution purification by extraction, was dismantled. About 42 tons of wastes were evacuated. Some wastes wen decontaminated by mechanical means other wastes with higher residual activity were stored for subsequent processing. The operation shows that dismantling of a hot cell is possible even if incorporated in an operating plant [fr

  4. Output-Feedback Model Predictive Control of a Pasteurization Pilot Plant based on an LPV model

    Science.gov (United States)

    Karimi Pour, Fatemeh; Ocampo-Martinez, Carlos; Puig, Vicenç

    2017-01-01

    This paper presents a model predictive control (MPC) of a pasteurization pilot plant based on an LPV model. Since not all the states are measured, an observer is also designed, which allows implementing an output-feedback MPC scheme. However, the model of the plant is not completely observable when augmented with the disturbance models. In order to solve this problem, the following strategies are used: (i) the whole system is decoupled into two subsystems, (ii) an inner state-feedback controller is implemented into the MPC control scheme. A real-time example based on the pasteurization pilot plant is simulated as a case study for testing the behavior of the approaches.

  5. Test operation of the uranium ore processing pilot plant and uranium conversion plant

    International Nuclear Information System (INIS)

    Suh, I.S.; Lee, K.I.; Whang, S.T.; Kang, Y.H.; Lee, C.W.; Chu, J.O.; Lee, I.H.; Park, S.C.

    1983-01-01

    For the guarantee of acid leaching process of the Uranium Ore Processing Pilot Plnat, the KAERI team performed the test operation in coorperation with the COGEMA engineers. The result of the operation was successful achieving the uranium leaching efficiency of 95%. Completing the guarentee test, a continuous test operation was shifted to reconform the reproducibility of the result and check the functions of every units of the pilot plant feeding the low-grade domestic ore, the consistency of the facility was conformed that the uranium can easily be dissolved out form the ore between the temperature range of 60degC-70degC for two hours of leaching with sulfuric acid and could be obtained the leaching efficiency of 92% to 95%. The uranium recovery efficiencies for the processes of extraction and stripping were reached to 99% and 99.6% respectively. As an alternative process for the separation of solid from the ore pulp, four of the Counter Current Decanters were shifted replacing the Belt Filter and those were connected in a series, which were not been tested during the guarantee operation. It was found out that the washing efficiencies of the ore pulp in each tests for the decanters were proportionally increased according to the quantities of the washing water. As a result of the test, it was obtained that washing efficiencies were 95%, 85%, 83% for the water to ore ratio of 3:1, 2:1, 1.5:1 respectively. (Author)

  6. Development of some operations in technological flowsheet for spent VVER fuel reprocessing at a pilot plant

    International Nuclear Information System (INIS)

    Lazarev, L.N.; Galkin, B.Ya; Lyubtsev, R.I.; Romanovskii, V.N.; Velikhov, E.P.

    1981-01-01

    The fuel reprocessing pilot plants for high active materials would permit the study and development or particular processing steps and flowsheet variations; in some cases, these experimental installations realize on a small scale practically all technological chains of large reprocessing plants. Such a fuel reprocessing pilot plant with capacity of 3 kg U/d has been built at V. G. Khlopin Radium Institute. The pilot plant is installed in the hot cell of radiochemical compartment, and is composed of the equipments for fuel element cutting and dissolving, the preparation of feed solution (clarification, correction), extraction reprocessing and the production of uranium, plutonium and neptunium concentrates, the complex processing of liquid and solid wastes and a special unit for gas purification and analysis. In the last few years, a series of experiments have been carried out on the reprocessing of spent VVER fuel. (J.P.N.)

  7. Integrated bicarbonate-form ion exchange treatment and regeneration for DOC removal: Model development and pilot plant study.

    Science.gov (United States)

    Hu, Yue; Boyer, Treavor H

    2017-05-15

    The application of bicarbonate-form anion exchange resin and sodium bicarbonate salt for resin regeneration was investigated in this research is to reduce chloride ion release during treatment and the disposal burden of sodium chloride regeneration solution when using traditional chloride-form ion exchange (IX). The target contaminant in this research was dissolved organic carbon (DOC). The performance evaluation was conducted in a completely mixed flow reactor (CMFR) IX configuration. A process model that integrated treatment and regeneration was investigated based on the characteristics of configuration. The kinetic and equilibrium experiments were performed to obtain required parameters for the process model. The pilot plant tests were conducted to validate the model as well as provide practical understanding on operation. The DOC concentration predicted by the process model responded to the change of salt concentration in the solution, and showed a good agreement with pilot plant data with less than 10% difference in terms of percentage removal. Both model predictions and pilot plant tests showed over 60% DOC removal by bicarbonate-form resin for treatment and sodium bicarbonate for regeneration, which was comparable to chloride-form resin for treatment and sodium chloride for regeneration. Lastly, the DOC removal was improved by using higher salt concentration for regeneration. Copyright © 2017 Elsevier Ltd. All rights reserved.

  8. The integrated in situ testing program for the Waste Isolation Pilot Plant (WIPP)

    International Nuclear Information System (INIS)

    Matalucci, R.V.

    1987-03-01

    The US Department of Energy (DOE) is developing the Waste Isolation Pilot Plant (WIPP) Project in southeastern New Mexico as a research and development (R and D) facility for examining the response of bedded (layered) salt to the emplacement of radioactive wastes generated from defense programs. The WIPP Experimental Program consists of a technology development program, including laboratory testing and theoretical analysis activities, and an in situ testing program that is being done 659 m underground at the project site. This experimental program addresses three major technical areas that concern (1) thermal/structural interactions, (2) plugging and sealing, and (3) waste package performance. To ensure that the technical issues involved in these areas are investigated with appropriate emphasis and timing, an in situ testing plan was developed to integrate the many activities and tasks associated with the technical issues of waste disposal. 5 refs., 4 figs

  9. Modification of the ventilation system at Waste Isolation Pilot Plant (WIPP)

    International Nuclear Information System (INIS)

    Sethi, S.C.

    1987-01-01

    The WIPP (Waste Isolation Pilot Plant) Project near Carlsbad, New Mexico, is a research and development project sponsored by the US Department of Energy, designed to demonstrate the safe disposal of radioactive waste. A mine (repository) is being developed 2,150 feet below the surface in a thick salt bed, which will serve as the disposal medium. The underground ventilation system for the WIPP project was originally designed based on a fixed project scope. The design criteria and ventilation requirements were developed for the performance of various activities as then envisioned towards the achievement of this goal. However, in light of new information and actual site-specific experience at WIPP leading to a clearer definition of the scope-related programs and activities, it was realized that the existing ventilation system may need to be modified

  10. Hydraulic Testing of Salado Formation Evaporites at the Waste Isolation Pilot Plant Site: Final Report

    Energy Technology Data Exchange (ETDEWEB)

    Beauheim, Richard L.; Domski, Paul S.; Roberts, Randall M.

    1999-07-01

    This report presents interpretations of hydraulic tests conducted in bedded evaporates of the Salado Formation from May 1992 through May 1995 at the Waste Isolation Pilot Plant (WIPP) site in southeastern New Mexico. The WIPP is a US Department of Energy research and development facility designed to demonstrate safe disposal of transuranic wastes from the nation's defense programs. The WIPP disposal horizon is located in the lower portion of the Permian Salado Formation. The hydraulic tests discussed in this report were performed in the WIPP underground facility by INTERA inc. (now Duke Engineering and Services, Inc.), Austin, Texas, following the Field Operations Plan and Addendum prepared by Saulnier (1988, 1991 ) under the technical direction of Sandia National Laboratories, Albuquerque, New Mexico.

  11. General description and production lines of the Egyptian fuel manufacturing pilot plant

    International Nuclear Information System (INIS)

    Zidan, W.I.; Elseaidy, I.M.

    1999-01-01

    The Egyptian Fuel Manufacturing Pilot Plant, FMPP, is a new facility, producing an MTR-type fuel elements required for the Egyptian Second Research Reactor, ETRR-2, as well as other plates or elements for an external clients with the same type and enrichment percent or lower, (LEU). General description is presented. The production lines in FMPP, which begin from uranium hexaflouride (UF 6 , 19.7±0.2 % U 235 by wt), aluminum powder, and nuclear grade 6061 aluminium alloy in sheets, bars, and rods with the different heat treatments and dimensions as a raw materials, are processed through a series of the manufacturing, inspection, and quality control plan to produce the final specified MTR-type fuel elements. All these processes and the product control in each step are presented. The specifications of the final product are presented. (author)

  12. Understanding and involvement: The key to public acceptance of the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    Kuntz, B.S.

    1991-01-01

    The Waste Isolation Pilot Plant (WIPP) is a research and development project of the United States Department of Energy (DOE) that is authorized under Public Law 96-164 ''to demonstrate the safe disposal of radioactive wastes resulting from defense programs of the United States.'' The transportation and disposal of transuranic radioactive wastes require an extensive public and media information program. This program must be able to respond to numerous information requests and concerns from state governments, citizens on the transportation routes, political leaders, public interest groups, emergency responders, and national and local media. The WIPP has developed a proactive program which aggressively provides information to these audiences through written and visual products, exhibits, presentations, and tours. As a result, thousands of interested parties have had their questions and concerns addressed, resulting in public understanding and support of the project's mission and its commitment to the safety of the public and the environment

  13. Historical Background on the Performance Assessment for the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    RECHARD, ROBERT P.

    1999-01-01

    In 1979, six years after selecting the Delaware Basin as a potential disposal area, Congress authorized the U.S. Department of Energy to build the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico, as a Research and development facility for the safe management storage, and disposal of waste contaminated with transuranic radioisotopes. In 1998, 19 years after authorization and after site selection, the U.S. Environmental Protection Agency (EPA) certified that the WIPP disposal system complied with its regulations. The EPA's decision was primarily based on the results from a performance. assessment conducted in 1996, which is summarized in this special issue of Reliability Engineering and System Safety. This performance assessment was the culmination of four preliminary performance assessments conducted between 1989 and 1992. This paper provides a historical setting and context for how the performance of the deep geologic repository at the WIPP was analyzed. Also included is background on political forces acting on the project

  14. Transporting transuranic waste to the Waste Isolation Pilot Plant: Risk and cost perspectives

    International Nuclear Information System (INIS)

    Biwer, B. M.; Gilette, J. L.; Poch, L. A.; Suermann, J. F.

    1999-01-01

    The Waste Isolation Pilot Plant (WIPP) is an authorized US Department of Energy (DOE) research and development facility constructed near the city of Carlsbad in southeastern New Mexico. The facility is intended to demonstrate the safe disposal of transuranic (TRU) radioactive waste resulting from US defense activities. Under the WIPP Land Withdrawal Act of 1992 (LWA), federal lands surrounding the WIPP facility were withdrawn from all public use and the title of those lands was transferred to the Secretary of Energy. The DOE's TRU waste is stored, and in some cases is still being generated, at 10 large-quantity and 13 small-quantity sites across the US. After applicable certification requirements have been met, the TRU waste at these sites will be sent to the WIPP to initiate the disposal phase of the facility, which according to current planning is projected to last for approximately 35 years

  15. Hydraulic Testing of Salado Formation Evaporites at the Waste Isolation Pilot Plant Site: Final Report

    International Nuclear Information System (INIS)

    Beauheim, Richard L.; Domski, Paul S.; Roberts, Randall M.

    1999-01-01

    This report presents interpretations of hydraulic tests conducted in bedded evaporates of the Salado Formation from May 1992 through May 1995 at the Waste Isolation Pilot Plant (WIPP) site in southeastern New Mexico. The WIPP is a US Department of Energy research and development facility designed to demonstrate safe disposal of transuranic wastes from the nation's defense programs. The WIPP disposal horizon is located in the lower portion of the Permian Salado Formation. The hydraulic tests discussed in this report were performed in the WIPP underground facility by INTERA inc. (now Duke Engineering and Services, Inc.), Austin, Texas, following the Field Operations Plan and Addendum prepared by Saulnier (1988, 1991 ) under the technical direction of Sandia National Laboratories, Albuquerque, New Mexico

  16. Technical Description Lillgrund Wind Power Plant. Lillgrund Pilot Project

    Energy Technology Data Exchange (ETDEWEB)

    Jeppsson, Joakim; Larsen, Poul Erik; Larsson, Aake [Vattenfall Vindkraft AB, Stockholm (Sweden)

    2008-09-15

    Lillgrund offshore wind power plant comprises 48 wind turbines, each rated at 2.3 MW, bringing the total wind farm capacity to 110 MW. The Lillgrund offshore wind power plant is located in a shallow area of Oeresund, 7 km off the coast of Sweden and 7 km south from the Oeresund Bridge connecting Sweden and Denmark. An average wind speed of around 8,5 m/s at hub height, combined with a relatively low water depth of 4 to 8 meters makes it economically feasible to build here. Vattenfall Vindkraft AB is the owner and operator of Lillgrund offshore wind power plant. Lillgrund is a Swedish pilot project supported by the Swedish Energy Agency. The bidding process was completed during 2005 and the offshore power plant was constructed in the period 2006 to 2007. The wind farm was constructed on time and has now been successfully operational since December 2007. There is, however, always potential for improvement and the aim of this report has been to determine and highlight these areas. It is worth noting out that only the electrical system and the foundations are tailor made at offshore wind power plants. The wind turbines are more or less standard products with none or very limited possibilities for project specific design changes. Geotechnical investigations are expensive and it can be difficult to balance the risks as well as the benefits of this expense in the early phases of a large infrastructure project. As a whole, the geotechnical surveys at Lillgrund proved to be useful. They identified potential issues, such as the fact that extra excavation was required for two of the foundations. It also revealed the location of a small number of boulders that would have to be removed. Vattenfall requested a complete study of the electrical system for Lillgrund to be delivered with the bids. That request was not met. Instead Siemens Wind Power began a complete electrical system study after being awarded the Contract. The electrical system study was completed during the

  17. Raft River binary-cycle geothermal pilot power plant final report

    Energy Technology Data Exchange (ETDEWEB)

    Bliem, C.J.; Walrath, L.F.

    1983-04-01

    The design and performance of a 5-MW(e) binary-cycle pilot power plant that used a moderate-temperature hydrothermal resource, with isobutane as a working fluid, are examined. Operating problems experienced and solutions found are discussed and recommendations are made for improvements to future power plant designs. The plant and individual systems are analyzed for design specification versus actual performance figures.

  18. 10-MWe pilot-plant-receiver panel test requirements document solar thermal test facility

    Energy Technology Data Exchange (ETDEWEB)

    1978-08-25

    Testing plans for a full-scale test receiver panel and supporting hardware which essentially duplicate both physically and functionally, the design planned for the Barstow Solar Pilot Plant are presented. Testing is to include operation during normal start and shutdown, intermittent cloud conditions, and emergencies to determine the panel's transient and steady state operating characteristics and performance under conditions equal to or exceeding those expected in the pilot plant. The effects of variations of input and output conditions on receiver operation are also to be investigated. Test hardware are described, including the pilot plant receiver, the test receiver assembly, receiver panel, flow control, electrical control and instrumentation, and structural assembly. Requirements for the Solar Thermal Test Facility for the tests are given. The safety of the system is briefly discussed, and procedures are described for assembly, installation, checkout, normal and abnormal operations, maintenance, removal and disposition. Also briefly discussed are quality assurance, contract responsibilities, and test documentation. (LEW)

  19. Strategic pilot for operator support system in nuclear power plant - design considerations

    International Nuclear Information System (INIS)

    Bucur, I.; Tatar, F.

    1999-01-01

    In order to improve the plant operational safety the development of an Operator Support System (OSS) is required. This system is intended to process data from nuclear systems and to provide adequate outputs to the plant operation staff. Before implementing this system, a strategic pilot should be produced as a demonstration of the technology. The strategic pilot could be considered as a means of building both skills and credibility in development and implementation of OSS. In any organization this project should be under plant management control with operation group involvement. This paper describes the managerial tasks that should be carried out to define, build and implement such a module. The main objectives, the functional requirements and the benefits of pilot implementation are revealed. Furthermore, the problem relating to the background at CNE-PROD Cernavoda is analyzed and the present achievements are pointed out. (authors)

  20. Radiation effects-prevalence of contributory risk factors a pilot study in Visakhapthnam steel plant

    International Nuclear Information System (INIS)

    Lakshman rao, K. V.

    2004-01-01

    Integrated Steel Plants contribute significant air pollution, water pollution and solid waste generation. Diverse occupational health hazards present is steel industry pose ill effects to the industrial workers. Occupational health services and research center (OHS and RC) of this plant established in the year 1992 to protect the health and well-being of all the employees working in different occupations. the primary role OHS and RC is to conduct periodical medical examinations, monitoring of the working environments, suggest the suitable personal protective equipment to the workers, evaluate risk factors, work practices, risk management and industrial toxicological studies. Dissemination of information related to occupational health and safety to the working population through regular educational sessions at the workplaces as at training and development center (T and DC) is also part of our services. The proneness for effects of exposure to ionizing radiation is enhanced by various factors related to the family history of chronic diseases, nutritional status of the individuals, the lifestyle factors apart from psycho-social factors like illiteracy, ignorance, negligence and inadequate utilization of personal protective equipment (PPE) at workplace. To evaluate the prevalence of such contributory risk factors, a pilot study has been conducted in Visakhapatnam Steel Plant. The data is obtained through routine periodical medical examination of workers at the Occupational Health Services Center through standard format. The study revealed statistically high prevalence of the risk factors and indicated the necessity of intensifying primary prevention methods in addition to environmental control and usage of PPE. (Author)

  1. New conceptual method in maintenance with application in cryogenics pilot plant (CPP)

    International Nuclear Information System (INIS)

    Anghel, Vasile

    2006-01-01

    Full text: This study concluded with a series of suggestions concerning the methodology of maintaining a Cryogenics Nuclear Plant where the maintenance is either fundamental or only of importance. The implementation of this methodology can be achieved in two main steps. The first step concerns the conception of the scientific basis for maintenance, while the second step regards the implementation. The first step describes the management of maintenance in conditions of quality, risk and cost constraints. The conditions are established on the basis of a project of research in maintenance. The second step notifies the aspects of design and technology in maintenance of nuclear industrial units. The nuclear complex technical systems of the Cryogenics Pilot Plant at ICSI - Rm Valcea implies the development of some dedicated software, to ensure the designing, realization and operation of the plant, and prototypes of integrated software modules, to ensure the systems operation during of the life cycle. The implementation method is based on vibration analyses and mechanical studies while a flexible data acquisition system for monitoring, and control must be developed as a platform to ensure a more precise diagnosis and prediction of machinery malfunction. With a flexible data acquisition and analysis system in operation it is possible to easily increase the number of input channels. (author)

  2. Radiation effects-prevalence of contributory risk factors a pilot study in Visakhapthnam steel plant

    Energy Technology Data Exchange (ETDEWEB)

    Lakshman rao, K. V.

    2004-07-01

    Integrated Steel Plants contribute significant air pollution, water pollution and solid waste generation. Diverse occupational health hazards present is steel industry pose ill effects to the industrial workers. Occupational health services and research center (OHS and RC) of this plant established in the year 1992 to protect the health and well-being of all the employees working in different occupations. the primary role OHS and RC is to conduct periodical medical examinations, monitoring of the working environments, suggest the suitable personal protective equipment to the workers, evaluate risk factors, work practices, risk management and industrial toxicological studies. Dissemination of information related to occupational health and safety to the working population through regular educational sessions at the workplaces as at training and development center (T and DC) is also part of our services. The proneness for effects of exposure to ionizing radiation is enhanced by various factors related to the family history of chronic diseases, nutritional status of the individuals, the lifestyle factors apart from psycho-social factors like illiteracy, ignorance, negligence and inadequate utilization of personal protective equipment (PPE) at workplace. To evaluate the prevalence of such contributory risk factors, a pilot study has been conducted in Visakhapatnam Steel Plant. The data is obtained through routine periodical medical examination of workers at the Occupational Health Services Center through standard format. The study revealed statistically high prevalence of the risk factors and indicated the necessity of intensifying primary prevention methods in addition to environmental control and usage of PPE. (Author)

  3. Systematic simulation of a tubular recycle reactor on the basis of pilot plant experiments

    Energy Technology Data Exchange (ETDEWEB)

    Paar, H; Narodoslawsky, M; Moser, A [Technische Univ., Graz (Austria). Inst. fuer Biotechnologie, Mikrobiologie und Abfalltechnologie

    1990-10-10

    Systematic simulatiom may decisively help in development and optimization of bioprocesses. By applying simulation techniques, optimal use can be made of experimental data, decreasing development costs and increasing the accuracy in predicting the behavior of an industrial scale plant. The procedure of the dialogue between simulation and experimental efforts will be exemplified in a case study. Alcoholic fermentation of glucose by zymomonas mobilis bacteria in a gasified turbular recycle reactor was studied first by systematic simulation, using a computer model based solely on literature data. On the base of the results of this simulation, a 0.013 m{sup 3} pilot plant reactor was constructed. The pilot plant experiments, too, were based on the results of the systematic simulation. Simulated and experimental data were well in agreement. The pilot plant experiments reiterated the trends and limits of the process as shown by the simulation results. Data from the pilot plant runs were then used to improve the simulation model. This improved model was subsequently used to simulate the performances of an industrial scale plant. The results of this simulation are presented. They show that the alcohol fermentation in a tubular recycle reactor is potentially advantageous to other reactor configurations, especially to continuous stirred tanks. (orig.).

  4. Report on 1979 result of Sunshine Project (detailed design). Part 1. Forty t/day solvolysis coal liquefaction pilot plant; 1979 nendo 40T/nichi solvolysis sekitan pilot plant shosai sekkei. 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1980-03-01

    The subject design documents are the compilation of the result of the design operation for the 'detailed design of 40 t/day class solvolysis coal liquefaction pilot plant'. The design of this pilot plant was conducted using, as the fundamental reference, the basic data provided by Kyushu National Industrial Research Institute and Kyushu University and the results of a contract research on '1 t/day class solvolysis coal liquefaction plant'. The subject detailed design was intended for Phase 1 centering on a single stage liquefaction - coal liquefaction (transformation into pitch) by solvolysis liquefaction reaction. The areas covered consists of the pre-treatment process, material mixing process, reaction process, reaction freezing process, coke separation process, SR recovery process, pitch refining process, utility facilities, and waste water treatment facilities. Incidentally, the processes for which the design operation has been completed this year, particularly the reaction process, coke separation process, SR recovery process, etc., are in the field untrodden technologically in the world; therefore, their design method is supposed to be established from the results of the R and D on coal liquefaction, '1 t/day class solvolysis coal liquefaction plant.' (NEDO)

  5. Report on 1979 result of Sunshine Project (detailed design). Part 1. Forty t/day solvolysis coal liquefaction pilot plant; 1979 nendo 40T/nichi solvolysis sekitan pilot plant shosai sekkei. 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1980-03-01

    The subject design documents are the compilation of the result of the design operation for the 'detailed design of 40 t/day class solvolysis coal liquefaction pilot plant'. The design of this pilot plant was conducted using, as the fundamental reference, the basic data provided by Kyushu National Industrial Research Institute and Kyushu University and the results of a contract research on '1 t/day class solvolysis coal liquefaction plant'. The subject detailed design was intended for Phase 1 centering on a single stage liquefaction - coal liquefaction (transformation into pitch) by solvolysis liquefaction reaction. The areas covered consists of the pre-treatment process, material mixing process, reaction process, reaction freezing process, coke separation process, SR recovery process, pitch refining process, utility facilities, and waste water treatment facilities. Incidentally, the processes for which the design operation has been completed this year, particularly the reaction process, coke separation process, SR recovery process, etc., are in the field untrodden technologically in the world; therefore, their design method is supposed to be established from the results of the R and D on coal liquefaction, '1 t/day class solvolysis coal liquefaction plant.' (NEDO)

  6. Development of the Risk-Based Inspection Techniques and Pilot Plant Activities

    International Nuclear Information System (INIS)

    Phillips, J.H.

    1997-01-01

    Risk-based techniques have been developed for commercial nuclear power plants. System boundaries and success criteria is defined using the probabilistic risk analysis or probabilistic safety analysis developed to meet the individual plant evaluation. Final ranking of components is by a plant expert panel similar to the one developed for maintenance rule. Components are identified as being high risk-significant or low-risk significant. Maintenance and resources are focused on those components that have the highest risk-significance. The techniques have been developed and applied at a number of pilot plants. Results from the first risk-based inspection pilot plant indicates that safety due to pipe failure can be doubled while the inspection reduced to about 80% when compared with current inspection programs. The reduction in inspection reduces the person-rem exposure resulting in further increases in safety. These techniques have been documented in publication by the ASME CRTD

  7. Verification of criticality Safety for ETRR-2 Fuel Manufacturing pilot Plant (FMPP) at Inshas

    International Nuclear Information System (INIS)

    Aziz, M.; Gadalla, A.A.; Orabi, G.

    2006-01-01

    The criticality safety of the fuel manufacturing pilot plant (FMPP) at inshas is studied and analyzed during normal and abnormal operation conditions. the multiplication factor during all stages of the manufacturing processes is determined. several accident scenarios were simulated and the criticality of these accidents were investigated. two codes are used in the analysis : MCNP 4 B code, based on monte Carlo method, and CITATION code , based on diffusion theory. the results are compared with the designer calculations and satisfactory agreement were found. the results of the study indicated that the safety of the fuel manufacturing pilot plant is confirmed

  8. Macroscopic mass and energy balance of a pilot plant anaerobic bioreactor operated under thermophilic conditions.

    Science.gov (United States)

    Espinosa-Solares, Teodoro; Bombardiere, John; Chatfield, Mark; Domaschko, Max; Easter, Michael; Stafford, David A; Castillo-Angeles, Saul; Castellanos-Hernandez, Nehemias

    2006-01-01

    Intensive poultry production generates over 100,000 t of litter annually in West Virginia and 9 x 10(6) t nationwide. Current available technological alternatives based on thermophilic anaerobic digestion for residuals treatment are diverse. A modification of the typical continuous stirred tank reactor is a promising process being relatively stable and owing to its capability to manage considerable amounts of residuals at low operational cost. A 40-m3 pilot plant digester was used for performance evaluation considering energy input and methane production. Results suggest some changes to the pilot plant configuration are necessary to reduce power consumption although maximizing biodigester performance.

  9. Development of a computer systems for operational data acquisition of uranium isotopic enrichment pilot plant

    International Nuclear Information System (INIS)

    Maia, W.M.C.

    1985-01-01

    A pilot plant for uranium enrichment using the jet nozzle process was transfered from Federal Republic of Germany to Brazil, to train Brazilian technicist in its operation and to improve the process. This pilot plant is monitored by a data acquisition system and the possibility of faulty events would cause serious dificulties, as far as maintenance is concerned (for instance, unvailable special components). It is described the development of a new system, which is proposed in order to minimize difficulties with maintenance that utilizes in the assembling integrated circuits of large scale of integration. It is controlled by a microcomputer. (Author) [pt

  10. Waste Isolation Pilot Plant transuranic wastes experimental characterization program: executive summary

    International Nuclear Information System (INIS)

    Molecke, M.A.

    1978-11-01

    A general overview of the Waste Isolation Pilot Plant transuranic wastes experimental characterization program is presented. Objectives and outstanding concerns of this program are discussed. Characteristics of transuranic wastes are also described. Concerns for the terminal isolation of such wastes in a deep bedded salt facility are divided into two phases, those during the short-term operational phase of the facility, and those potentially occurring in the long-term, after decommissioning of the repository. An inclusive summary covering individual studies, their importance to the Waste Isolation Pilot Plant, investigators, general milestones, and comments are presented

  11. Continued oversight of the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    Peake, R. Thomas

    2014-01-01

    The United States Environmental Protection Agency (EPA) developed environmental standards applicable to the disposal of defence-related transuranic wastes at the US Department of Energy's (DOE) Waste Isolation Pilot Plant (WIPP). By statute, EPA also serves as the regulator and implements these standards at WIPP, which has been in operation since 1999. The general environmental standards are set forth in the Agency's 40 Code of Federal Regulations (CFR), Part 191 Environmental Radiation Protection Standards for the Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Wastes (US NARA, 1985). These standards are implemented by site-specific compliance criteria at 40 CFR 194 (US NARA, 1996). The repository waste area is ∼650 meters below ground surface in a thick bedded salt formation that dips from west to east at ∼1 deg.. WIPP is located in the Chihuahuan Desert of south-eastern New Mexico, where the annual precipitation averages between 25 and 40 centimetres and there is high evapotranspiration. Much of the area around WIPP is federal land, managed by the Bureau of Land Management, and the area is sparsely populated. The transuranic waste disposed of at WIPP consists of materials such as radioactive sludges, soils and laboratory materials (e.g. chemical mixtures, contaminated glove boxes, paper and glass). Wastes are typically not treated unless necessary for shipping purposes (e.g. to limit hydrogen build-up). The waste is contaminated with plutonium, americium and other radionuclides, including some caesium and strontium. Transuranic waste is defined as waste with radionuclides heavier than uranium containing more than 3 700 Bq (100 nanocuries) of alpha-emitting transuranic isotopes per gram of waste; isotopes must have half-lives greater than 20 years. The WIPP Land Withdrawal Act limits the total disposal volume to ∼177 000 cubic meters (6.2 million cubic feet) and creates two categories of waste based on operational

  12. Laboratory Testing of Waste Isolation Pilot Plant Surrogate Waste Materials

    Science.gov (United States)

    Broome, S.; Bronowski, D.; Pfeifle, T.; Herrick, C. G.

    2011-12-01

    The Waste Isolation Pilot Plant (WIPP) is a U.S. Department of Energy geological repository for the permanent disposal of defense-related transuranic (TRU) waste. The waste is emplaced in rooms excavated in the bedded Salado salt formation at a depth of 655 m below the ground surface. After emplacement of the waste, the repository will be sealed and decommissioned. WIPP Performance Assessment modeling of the underground material response requires a full and accurate understanding of coupled mechanical, hydrological, and geochemical processes and how they evolve with time. This study was part of a broader test program focused on room closure, specifically the compaction behavior of waste and the constitutive relations to model this behavior. The goal of this study was to develop an improved waste constitutive model. The model parameters are developed based on a well designed set of test data. The constitutive model will then be used to realistically model evolution of the underground and to better understand the impacts on repository performance. The present study results are focused on laboratory testing of surrogate waste materials. The surrogate wastes correspond to a conservative estimate of the degraded containers and TRU waste materials after the 10,000 year regulatory period. Testing consists of hydrostatic, uniaxial, and triaxial tests performed on surrogate waste recipes that were previously developed by Hansen et al. (1997). These recipes can be divided into materials that simulate 50% and 100% degraded waste by weight. The percent degradation indicates the anticipated amount of iron corrosion, as well as the decomposition of cellulosics, plastics, and rubbers. Axial, lateral, and volumetric strain and axial and lateral stress measurements were made. Two unique testing techniques were developed during the course of the experimental program. The first involves the use of dilatometry to measure sample volumetric strain under a hydrostatic condition. Bulk

  13. Practical and Scholarly Implications of Information Behaviour Research: A Pilot Study of Research Literature

    Science.gov (United States)

    Koh, Kyungwon; Rubenstein, Ellen; White, Kelvin

    2015-01-01

    Introduction: This pilot study examined how current information behaviour research addresses the implications and potential impacts of its findings. The goal was to understand what implications and contributions the field has made and how effectively authors communicate implications of their findings. Methods: We conducted a content analysis of 30…

  14. A Pilot Study Investigating the Effects of Advanced Nuclear Power Plant Control Room Technologies: Methods and Qualitative Results

    Energy Technology Data Exchange (ETDEWEB)

    BLanc, Katya Le [Idaho National Lab. (INL), Idaho Falls, ID (United States); Powers, David [Idaho National Lab. (INL), Idaho Falls, ID (United States); Joe, Jeffrey [Idaho National Lab. (INL), Idaho Falls, ID (United States); Spielman, Zachary [Idaho National Lab. (INL), Idaho Falls, ID (United States); Rice, Brandon [Idaho National Lab. (INL), Idaho Falls, ID (United States); Fitzgerald, Kirk [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2015-08-01

    Control room modernization is an important part of life extension for the existing light water reactor fleet. None of the 99 currently operating commercial nuclear power plants in the U.S. has completed a full-scale control room modernization to date. Nuclear power plant main control rooms for the existing commercial reactor fleet remain significantly analog, with only limited digital modernizations. Upgrades in the U.S. do not achieve the full potential of newer technologies that might otherwise enhance plant and operator performance. The goal of the control room upgrade benefits research is to identify previously overlooked benefits of modernization, identify candidate technologies that may facilitate such benefits, and demonstrate these technologies through human factors research. This report describes a pilot study to test upgrades to the Human Systems Simulation Laboratory at INL.

  15. Analytical technology in support of the Waste Isolation Pilot Plant (WIPP)

    International Nuclear Information System (INIS)

    Villareal, R.

    1994-01-01

    The need for long-term disposal of defense-related transuranic (TRU) wastes became apparent as the DOE recognized the environmental consequences of maintaining waste storage facilities designed for short or interim storage periods, not long-term storage. In 1979, Congress authorized the Waste Isolation Pilot Plant (WIPP), a research and development facility and full-scale pilot plant, to demonstrate the safe management, storage, and disposal of TRU wastes. Environmental Protection Agency (EPA) regulations governing disposal of TRU wastes in 40 CFR 191 require that TRU waste disposal systems be designed to limit migration of radionuclides to the accessible environment for 10,000 years based on performance assessment results. The actinide source-term waste test program (STTP) is an experiment designed to quantitatively measure the time-dependent concentrations of plutonium, uranium, neptunium, thorium, and americium in TRU wastes immersed in brines that simulate the chemistry that may occur in WIPP disposal rooms, partially or completely contacted with brines. The total concentration of each actinide in brine is the sum of its dissolved and colloidally suspended components, as determined by variables including pcH, oxidation-reduction potential (Eh), chelating and complexing agents, sorption capacity, and colloidal suspension capabilities. To determine the effect of influencing variables on the concentration of actinides in WIPP brines, several TRU waste types will be characterized and loaded into specially designed noncorrosive test containers filled with brine containing additives to enhance the action of each influencing variable. The test container brine and headspace gases will be analyzed

  16. Plant Research Department annual report 2003

    DEFF Research Database (Denmark)

    Kossmann, J.; Jakobsen, Iver; Nielsen, K.K.

    2004-01-01

    In 2003 the Plant Research Department (PRD) at Risø National Laboratory was involved in establishing the consortium Plant Biotech Denmark, which is unifying most of the Danish Plant Biotechnology activities. Within the consortium, PRD has the uniqueopportunity to be the only life science department...... to genes, which are widely applicable in the life sciences, such as non-invasive and non-destructive technologies to determine metabolite concentrationswith high spatial and temporal resolution. The Plant Research Department applies these and state-of-the-art technologies to increase knowledge to develop...... located in an environment that is largely dominated by physicists. PRD is challenged to optimally interface Plant Biology with the different fields of expertise that are established at Risø NationalLaboratory. These activities are mainly related to develop novel post-genomic tools to assign function...

  17. Nordic research infrastructures for plant phenotyping

    Directory of Open Access Journals (Sweden)

    Kristiina Himanen

    2018-03-01

    Full Text Available Plant phenomics refers to the systematic study of plant phenotypes. Together with closely monitored, controlled climates, it provides an essential component for the integrated analysis of genotype-phenotype-environment interactions. Currently, several plant growth and phenotyping facilities are under establishment globally, and numerous facilities are already in use. Alongside the development of the research infrastructures, several national and international networks have been established to support shared use of the new methodology. In this review, an overview is given of the Nordic plant phenotyping and climate control facilities. Since many areas of phenomics such as sensor-based phenotyping, image analysis and data standards are still developing, promotion of educational and networking activities is especially important. These facilities and networks will be instrumental in tackling plant breeding and plant protection challenges. They will also provide possibilities to study wild species and their ecological interactions under changing Nordic climate conditions.

  18. Investigations into the operating behavior of separation nozzle cascades for uranium-235 enrichment in a 10-stage pilot plant

    International Nuclear Information System (INIS)

    Bley, P.; Hein, H.; Linder, G.

    1984-03-01

    The separation nozzle method developed by the Karlsruhe Nuclear Research Center is based on the centrifugal force in a curved jet consisting of uranium hexafluoride and a light auxiliary gas. To determine in experiments the operating and controlling behavior of separation nozzle cascades a 10-stage pilot plant was erected some year ago. This plant was transferred to the Centro de Desenvolvimento da Tecnologia Nuclear (CDTN) in Belo Horizonte as a donation made within the framework of the German-Brazilian Agreement on scientific cooperation in the field of uranium enrichment. The plant previously equipped with single deflection systems was modified to operate with the double deflection system envisaged for commercial plants. A controlling concept meanwhile developed and improved for separation nozzle cascades equipped with single and double deflection systems was verified experimentally and optimized at the pilot plant of the CDTN. A comparison of the experimental operating behavior with the operating behavior calculated by simulation programs has confirmed the faithfulness of simulation of the computer codes developed to apply to cascades with double deflection systems as well. (orig.) [de

  19. Investigation of Parameters Affecting Gypsum Dewatering Properties in a Wet Flue Gas Desulphurization Pilot Plant

    DEFF Research Database (Denmark)

    Hansen, Brian Brun; Kiil, Søren

    2012-01-01

    of impurities (0.002 M Al2F6; 50 g quartz/L; 0.02 M Al3+, and 0.040 M Mg2+) were investigated. In addition, slurry from a full-scale wet FGD plant, experiencing formation of flat shaped crystals and poor gypsum dewatering properties, was transferred to the pilot plant to test if the plant would now start...... to time. In this work, the particle size distribution, morphology, and filtration rate of wet FGD gypsum formed in a pilot-scale experimental setup, operated in forced oxidation mode, have been studied. The influence of holding tank residence time (10–408 h), solids content (30–169 g/L), and the presence...... to produce low quality gypsum. The crystals formed in the pilot plant, on the basis of the full-scale slurry did, however, show acceptable filtration rates and crystal morphologies closer to the prismatic crystals from after pilot plant experiments with demineralized water. The gypsum slurry filtration rates...

  20. Water-gas shift (WGS) Operation of Pre-combustion CO2 Capture Pilot Plant at the Buggenum IGCC

    NARCIS (Netherlands)

    Van Dijk, H.A.J.; Damen, K.; Makkee, M.; Trapp, C.

    2014-01-01

    In the Nuon/Vattenfall CO2 Catch-up project, a pre-combustion CO2 capture pilot plant was built and operated at the Buggenum IGCC power plant, the Netherlands. The pilot consist of sweet water-gas shift, physical CO2 absorption and CO2 compression. The technology performance was verified and

  1. The Nonuse, Misuse, and Proper Use of Pilot Studies in Experimental Evaluation Research

    Science.gov (United States)

    Westlund, Erik; Stuart, Elizabeth A.

    2017-01-01

    This article discusses the nonuse, misuse, and proper use of pilot studies in experimental evaluation research. The authors first show that there is little theoretical, practical, or empirical guidance available to researchers who seek to incorporate pilot studies into experimental evaluation research designs. The authors then discuss how pilot…

  2. Pilot-plant cultivation of Streptomyces griseus producing homologues of nonactin by precursor-directed biosynthesis and their identification by LC/MS-ESI

    Czech Academy of Sciences Publication Activity Database

    Řezanka, Tomáš; Prell, Aleš; Spížek, Jaroslav; Sigler, Karel

    2010-01-01

    Roč. 63, č. 8 (2010), s. 524-529 ISSN 0021-8820 R&D Projects: GA MŠk 1M06011 Institutional research plan: CEZ:AV0Z50200510 Keywords : liquid chromatography/MS-ESI * pilot-plant cultivation * precursor-directed biosynthesis Subject RIV: EE - Microbiology, Virology Impact factor: 1.628, year: 2010

  3. Studying on design of a complete pilot plant for processing sandstone ores in Pa Lua-Pa Rong area

    International Nuclear Information System (INIS)

    Le Quang Thai; Tran Van Son; Vu Khac Tuan; Tran The Dinh; Trinh Nguyen Quynh; Doan Thi Mo; Nguyen Hong Ha; Bui Thi Bay; Pham Minh Tuan; Than Van Lien

    2015-01-01

    Design, construction and operation of a pilot for processing uranium containing ores are important stages in the process of project development of uranium production from ores because uranium contained minerals and the composition of minerals are unstable factors. In this case, pilot needs to be a simulation of a plant in the future, but with upgrade equipment compared that at laboratory scale. Results of lab research were used to select the most appropriate process for ore processing and selection of equipment for each stages. In the circumstance when there has been a lack of experience in processing uranium ores in Vietnam, the design and construction of such a pilot with completed technological procedures are essential. The main purpose of this work is to verify results of lab researches and optimize operational parameters of the process. In addition, several purposes were also considered such as study on the effects of solution circulation/recycling and accumulation of impurities in a long run; obtain necessary and sufficient information for design, cost estimate for investment and operation. The pilot only can achieve the expected objectives when ore sources (including reserves and characteristics) are determined; a complete technological process for obtaining technical uranium (yellowcake) is designed; investment and operational capitals are estimated and these estimates show the costs and benefits of the process. In this article, the authors will focus on the presentation of research results, including data on ore, process technology, material balance, pilot scale, the basic parameters of equipment, installation diagram of equipment, construction, power and water needs identification, preliminary calculation of investment and operational costs. (author)

  4. Plant research '79: report of the Michigan State University, Department of Energy, Plant Research Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    1979-01-01

    Botanical research conducted at MSU during 1979 is described. Areas of study include cell wall biosynthesis, hormonal regulation, responses of plants to environmental stresses, and molecular studies. (ACR)

  5. Pilot plant studies of the bioconversion of cellulose and production of ethanol

    Energy Technology Data Exchange (ETDEWEB)

    Wilke, C.R.

    1977-09-30

    Work for the period July 1 to September 30, 1977 is summarized briefly. Results of the following studies are reported: analysis and evaluation of potential raw materials--chemical analysis of the Kudzu plant and effect of NO/sub x/ pretreatments on the hydrolysis of wheat straw; utilization of hemicellulose sugars; process design and economic studies--hydrolysis process and ethanol fermentation; pilot plant process development and design studies--enhanced cellulase production and continuous hydrolysis. (JGB)

  6. The design of a modular pilot plant based on the adsorber loop concept

    International Nuclear Information System (INIS)

    Koske, P.H.; Ohlrogge, K.

    1984-01-01

    The main design criteria for a pilot plant producing about 100 t uranium per year from seawater are discussed. The application of the ''adsorber loop concept'' for the contact between seawater and the adsorber granulate enables the employment of high seawater velocities. The seawater flow is accomplished by active pumping and the plant is supposed to be operating far from shores. Besides some informations on the theoretical background the essential engineering considerations are presented. (orig.) [de

  7. Modernization and enlarging of the Marcoule pilot plant for R and D

    International Nuclear Information System (INIS)

    Calame-Longjean, A.; Revol, G.; Roux, J.P.; Ranger, G.

    1987-01-01

    The aim of the pilot plant is the testing of process and equipment in actual conditions with spent fuels on a half-industrial scale and for a significant time. From 1963 to 1983 more than 11t of spent fuels (mainly from fast reactors) were reprocessed. Since 1983 is modernized and enlarged and the new plant of the TOR project (treatment of oxides from fast reactors) are described [fr

  8. A pilot study of MD (psychiatry) theses-based research.

    Science.gov (United States)

    Srivastava, Shrikant; Agarwal, Vivek; Subramanyam, Alka; Srivastava, Mona; Sathyanarayana Rao, T S; Rao, G Prasad; Khurana, Hitesh; Singh, Archana

    2018-01-01

    Undertaking a research project is mandatory for MD Psychiatry trainees. The present study was undertaken to assess the type of research activity being undertaken as part of MD Psychiatry dissertation, and its contribution to national and international literature. Three medical colleges supplied the data about the topic, names of the supervisor and the candidate, collaboration, funding accrued, and publication details of MD-based research carried out between years 2000 and 2010 inclusive; 95 records were collected for the final analysis. The details of the publications provided were cross-checked on the internet, which would have taken care of missed publications as well. Most studies were single-point assessment clinical studies. Only 2 studies had been funded, 11 had collaboration with other departments within the same institute, and 5 had inter-institute collaborations. Majority of the studies were not published. Only 30 were published as full paper and 9 as abstracts. Of these 30 full publications, only 3 were published in journals having JCI impact factor values (1.4, 1.3, and 1.4, respectively). The main finding of this pilot study was that MD-based research has low contribution to the national and international literature, and those articles which are published are in low impact journals. Suggestions for modifying this state of affairs are discussed.

  9. Use of phosphorus release batch tests for modelling an EBPR pilot plant

    DEFF Research Database (Denmark)

    Tykesson, E.; Aspegren, H.; Henze, Mogens

    2002-01-01

    The aim of this study was to evaluate how routinely performed phosphorus release tests could be used when modelling enhanced biological phosphorus removal (EBPR) using activated sludge models such as ASM2d. A pilot plant with an extensive analysis programme was used as basis for the simulations...

  10. Drying and purification of natural gas by clinoptilolite on an experimental pilot plant

    Energy Technology Data Exchange (ETDEWEB)

    Tsitsishvili, G V; Urotadze, S L; Lukin, V D; Bagirov, R M

    1976-02-01

    The paper deals with the process of the drying and purification of natural gas from CO/sub 2/ on an experimental pilot plant using the natural zeolite clinoptilolite. On the basis of the obtained data the dynamic activity of clinoptilolite against water and CO/sub 2/ has been calculated.

  11. Hydraulic testing of Salado Formation evaporites at the Waste Isolation Pilot Plant site: Second interpretive report

    Energy Technology Data Exchange (ETDEWEB)

    Beauheim, R.L. [Sandia National Labs., Albuquerque, NM (United States); Roberts, R.M.; Dale, T.F.; Fort, M.D.; Stensrud, W.A. [INTERA, Inc., Austin, TX (United States)

    1993-12-01

    Pressure-pulse, constant-pressure flow, and pressure-buildup tests have been performed in bedded evaporites of the Salado Formation at the Waste Isolation Pilot Plant (WIPP) site to evaluate the hydraulic properties controlling brine flow through the Salado. Transmissivities have been interpreted from six sequences of tests conducted on five stratigraphic intervals within 15 m of the WIPP underground excavations.

  12. Continuous operation of a pilot plant for the production of beryllium oxide

    Energy Technology Data Exchange (ETDEWEB)

    Costa, T C; Amaral, S; Silveira, C M.S.; de Oliveira, A P [Instituto de Tecnologia, Governador Valadares (Brazil)

    1975-12-01

    A method of obtaining beryllium oxide with a purity of 99,2% was developed in a pilot plant with a capacity of 7 tons per month destined to operate continuously. The operation market prospects and control of production with the objective of obtaining internacional technical grade beryllium oxide are discussed.

  13. Retrieval of canistered experimental waste at the waste isolation pilot plant

    International Nuclear Information System (INIS)

    Stinebaugh, R.E.

    1979-07-01

    To assess the suitability of bedded salt for nuclear waste disposal, an extensive experimental program will be implemented at the Waste Isolation Pilot Plant. In order to evaluate experimental results, it will be necessary to recover certain of these experiments for postmortem examination and analysis. This document describes the equipment and procedures used to effect recovery of one category of WIPP experiments

  14. Waste Isolation Pilot Plant Geotechnical Analysis Report for July 2005 - June 2006, Volume 2, Supporting Data

    Energy Technology Data Exchange (ETDEWEB)

    Washington TRU Solutions LLC

    2007-03-25

    This report is a compilation of geotechnical data presented as plots for each active instrument installed in the underground at the Waste Isolation Pilot Plant (WIPP) through June 30, 2006. A summary of the geotechnical analyses that were performed using the enclosed data is provided in Volume 1 of the Geotechnical Analysis Report (GAR).

  15. Continuous operation of a pilot plant for the production of beryllium oxide

    International Nuclear Information System (INIS)

    Costa, T.C.; Amaral, S.; Silveira, C.M.S.; Oliveira, A.P. de

    1975-01-01

    A method of obtaining beryllium oxide with a purity of 99,2% was developed in a pilot plant with a capacity of 7 tons per month destined to operate continuously. The operation market prospects and control of production with the objective of obtaining internacional technical grade beryllium oxide are discussed [pt

  16. Electrodialytic remediation of CCA-treated waste wood in a 2 m3 pilot plant

    DEFF Research Database (Denmark)

    Christensen, Iben Vernegren; Pedersen, Anne Juul; Ottosen, Lisbeth M.

    2006-01-01

    Waste wood that has been treated with chromated-copper-arsenate (CCA) poses a potential environmental problem due to the content of copper, chromium and arsenic. A pilot plant for electrodialytic remediation of up to 2 m3 wood has been designed and tested and the results are presented here. Sever...

  17. WIPP conceptual design report. Addendum A. Design calculations for Waste Isolation Pilot Plant (WIPP)

    International Nuclear Information System (INIS)

    1977-04-01

    The design calculations for the Waste Isolation Pilot Plant (WIPP) are presented. The following categories are discussed: general nuclear calculations; radwaste calculations; structural calculations; mechanical calculations; civil calculations; electrical calculations; TRU waste surface facility time and motion analysis; shaft sinking procedures; hoist time and motion studies; mining system analysis; mine ventilation calculations; mine structural analysis; and miscellaneous underground calculations

  18. Radioactive Waste Disposal Pilot Plant concept for a New Mexico site

    International Nuclear Information System (INIS)

    Weart, W.D.

    1976-01-01

    Twenty years of investigation have shown that disposal of nuclear wastes in deep salt formations is the surest means of isolating these wastes from the biosphere for the extremely long period of time required. A large scale demonstration of this capability will soon be provided by a Radioactive Waste Disposal Pilot Plant (RWDPP) to be developed in southeastern New Mexico. Initially, the pilot plant will accept only ERDA generated waste; high level waste from the commercial power reactor fuel cycle will eventually be accommodated in the pilot plant and the initial RWDPP design will be compatible with this waste form. Selection of a specific site and salt horizon will be completed in June 1976. Conceptual design of the RWDPP and assessment of its environmental impact will be completed by June 1977. Construction is expected to start in 1978 with first waste accepted in 1982. The present concept develops disposal areas for all nuclear waste types in a single salt horizon about 800 meters deep. This single level can accommodate all low level and high level waste generated in the United States through the year 2010. A major constraint on the RWDPP design is the ERDA requirement that all waste be ''readily'' retrievable during the duration of pilot plant operation

  19. Not-from-concentrate pilot plant ‘Wonderful’ cultivar pomegranate juice changes: Volatiles

    Science.gov (United States)

    Pilot plant ultrafiltration was used to mimic the dominant U.S. commercial pomegranate juice extraction method (hydraulic pressing whole fruit), to deliver a not-from-concentrate (NFC) juice that was high-temperature short-time pasteurized and stored at 4 and 25 °C. Recovered were 46 compounds, of ...

  20. Waste Isolation Pilot Plant Geotechnical Analysis Report for July 2005 - June 2006, Volume 2, Supporting Data

    International Nuclear Information System (INIS)

    2007-01-01

    This report is a compilation of geotechnical data presented as plots for each active instrument installed in the underground at the Waste Isolation Pilot Plant (WIPP) through June 30, 2006. A summary of the geotechnical analyses that were performed using the enclosed data is provided in Volume 1 of the Geotechnical Analysis Report (GAR).

  1. Hydraulic testing of Salado Formation evaporites at the Waste Isolation Pilot Plant site: Second interpretive report

    International Nuclear Information System (INIS)

    Beauheim, R.L.; Roberts, R.M.; Dale, T.F.; Fort, M.D.; Stensrud, W.A.

    1993-12-01

    Pressure-pulse, constant-pressure flow, and pressure-buildup tests have been performed in bedded evaporites of the Salado Formation at the Waste Isolation Pilot Plant (WIPP) site to evaluate the hydraulic properties controlling brine flow through the Salado. Transmissivities have been interpreted from six sequences of tests conducted on five stratigraphic intervals within 15 m of the WIPP underground excavations

  2. Pasteurization of strawberry puree using a pilot plant pulsed electric fields (PEF) system

    Science.gov (United States)

    The processing of strawberry puree by pulsed electric fields (PEF) in a pilot plant system has never been evaluated. In addition, a method does not exist to validate the exact number and shape of the pulses applied during PEF processing. Both buffered peptone water (BPW) and fresh strawberry puree (...

  3. Resource conservation and recovery act draft hazardous waste facility permit: Waste Isolation Pilot Plant (WIPP)

    International Nuclear Information System (INIS)

    1993-08-01

    Volume I contains the following attachments for Module II: waste analysis plan; quality assurance program plan for the Waste Isolation Pilot Plant (WIPP) Experiment Waste Characterization Program(QAPP); WIPP Characterization Sampling and Analysis Guidance Manual (Plan)(SAP); and no migration Determination Requirement Summary (NMD)

  4. Developments in the pre-combustion CO2 capture pilot plant at the Buggenum IGCC

    NARCIS (Netherlands)

    Damen, K.; Gnutek, R.; Kaptein, J.; Nannan, N.R.; Oyarzun, B.; Trapp, C.; Colonna, P.; Van Dijk, E.; Gross, J.; Bardow, A.

    2011-01-01

    N.V. Nuon (part of the Vattenfall Group) operates an IGCC in Buggenum and is developing a multi-fuel IGCC with CO2 capture and storage (Nuon Magnum) in Eemshaven, the Netherlands. In order to prepare for large-scale application of CO2 capture and storage, a CO2 capture pilot plant is constructed at

  5. Improvement of water treatment pilot plant with Moringa oleifera extract as flocculant agent.

    Science.gov (United States)

    Beltrán-Heredia, J; Sánchez-Martín, J

    2009-05-01

    Moringa oleifera extract is a high-capacity flocculant agent for turbidity removal in surface water treatment. A complete study of a pilot-plant installation has been carried out. Because of flocculent sedimentability of treated water, a residual turbidity occured in the pilot plant (around 30 NTU), which could not be reduced just by a coagulation-flocculation-sedimentation process. Because of this limitation, the pilot plant (excluded filtration) achieved a turbidity removal up to 70%. A slow sand filter was put in as a complement to installation. A clogging process was characterized, according to Carman-Kozeny's hydraulic hypothesis. Kozeny's k parameter was found to be 4.18. Through fouling stages, this k parameter was found to be up to 6.36. The obtained data are relevant for the design of a real filter in a continuous-feeding pilot plant. Slow sand filtration is highly recommended owing to its low cost, easy-handling and low maintenance, so it is a very good complement to Moringa water treatment in developing countries.

  6. Double stage dry-wet-fermentation - start-up of a pilot biogas plant

    International Nuclear Information System (INIS)

    Buschmann, Jeannette; Busch, Gunter; Burkhardt, Marko

    2009-01-01

    The Brandenburg University of Technology (BTU) has developed a double stage dry-wet fermentation process for fast and safe anaerobic degradation. Originally designed for treatment of organic wastes, this process allows using a wide variety of solid biodegradable materials. The dividing of hydrolysis and methanation in this process, allows an optimization of the different steps of biogas generation separately. The main advantages of the process are the optimum process control, an extremely stable process operation and a high gas productivity and quality. Compared to conventional processes, the retention times within the percolation stage (hydrolysis) are reduced considerably. In cooperation with the engineering and consulting company GICON, the technology was qualified further to an industrial scale. In 2007 a pilot plant, and, simultaneously, an industrial plant were built by GICON based on this double stage technology. Based on practical experience from the operation of laboratory fermentation plants, the commissioning of the pilot plant was planned, controlled and monitored by our institution. The start-up of a biogas plant of this type focuses mainly on the inoculation the of methane reactor. The growth of microbial populations and generation of a stable biocenosis within the methane reactor is essential and affects the duration of starting period as well as the methanation efficiency a long time afterwards. This paper concerns with start-up of a pilot biogas plant and discusses particular occurrences and effects during this period. (author)

  7. Test Results and Comparison of Triaxial Strength Testing of Waste Isolation Pilot Plant Clean Salt

    Energy Technology Data Exchange (ETDEWEB)

    Buchholz, Stuart A. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2016-12-01

    This memorandum documents laboratory thermomechanical triaxial strength testing of Waste Isolation Pilot Plant (WIPP) clean salt. The limited study completed independent, adjunct laboratory tests in the United States to assist in validating similar testing results being provided by the German facilities. The testing protocol consisted of completing confined triaxial, constant strain rate strength tests of intact WIPP clean salt at temperatures of 25°C and 100°C and at multiple confining pressures. The stratigraphy at WIPP also includes salt that has been labeled “argillaceous.” The much larger test matrix conducted in Germany included both the so-called clean and argillaceous salts. When combined, the total database of laboratory results will be used to develop input parameters for models, assess adequacy of existing models, and predict material behavior. These laboratory studies are also consistent with the goals of the international salt repository research program. The goal of this study was to complete a subset of a test matrix on clean salt from the WIPP undertaken by German research groups. The work was performed at RESPEC in Rapid City, South Dakota. A rigorous Quality Assurance protocol was applied, such that corroboration provides the potential of qualifying all of the test data gathered by German research groups.

  8. Research of the Power Plant Operational Modes

    Directory of Open Access Journals (Sweden)

    Koismynina Nina M.

    2017-01-01

    Full Text Available In this article the algorithm of the power plant operational modes research is offered. According to this algorithm the program for the modes analysis and connection power transformers choice is developed. The program can be used as educational means for studying of the power plant electric part, at the same time basic data are provided. Also the program can be used for the analysis of the working power plants modes. Checks of the entered data completeness and a choice correctness of the operational modes are provided in the program; in all cases of a deviation from the correct decisions to the user the relevant information is given.

  9. EURObservational Research Programme: the Heart Failure Pilot Survey (ESC-HF Pilot)

    DEFF Research Database (Denmark)

    Maggioni, Aldo P; Dahlström, Ulf; Filippatos, Gerasimos

    2010-01-01

    The primary objective of the new ESC-HF Pilot Survey was to describe the clinical epidemiology of outpatients and inpatients with heart failure (HF) and the diagnostic/therapeutic processes applied across 12 participating European countries. This pilot study was specifically aimed at validating...

  10. EURObservational Research Programme : The Heart Failure Pilot Survey (ESC-HF Pilot)

    NARCIS (Netherlands)

    Maggioni, Aldo P.; Dahlstrom, Ulf; Filippatos, Gerasimos; Chioncel, Ovidiu; Crespo Leiro, Marisa; Drozdz, Jaroslaw; Fruhwald, Friedrich; Gullestad, Lars; Logeart, Damien; Metra, Marco; Parissis, John; Persson, Hans; Ponikowski, Piotr; Rauchhaus, Mathias; Voors, Adriaan A.; Nielsen, Olav Wendelboe; Zannad, Faiez; Tavazzi, Luigi

    2010-01-01

    The primary objective of the new ESC-HF Pilot Survey was to describe the clinical epidemiology of outpatients and inpatients with heart failure (HF) and the diagnostic/therapeutic processes applied across 12 participating European countries. This pilot study was specifically aimed at validating the

  11. Plant Research Department annual report 2002

    DEFF Research Database (Denmark)

    2003-01-01

    concentrations in the atmosphere. Finally, activities are increasing to establish systems thatoptimize the production of energy from biomass in order to promote sustainability in industrial societies. The department is divided into five research programmes that are linked through their individual expertise...... to the optimal use of crops. One programme is devoted to improve the market value of plant products. Plants with enhanced nutritional value or that contain novel renewable resources are designed to add value to the European Agro-Industries.A fifth programme ultimately is studying the effects of the future......The Plant Research Department at Risø National Laboratory has the unique opportunity to be the only life science department located in an environment that is largely dominated by physicists. In 2002 increasing numbers of projects have been initiated thatestablish interdisciplinary research in order...

  12. Pilot plant UF6 to UF4 test operations report

    International Nuclear Information System (INIS)

    Bicha, W.J.; Fallings, M.; Gilbert, D.D.; Koch, G.E.; Levine, P.J.; McLaughlin, D.F.; Nuhfer, K.R.; Reese, J.C.

    1987-02-01

    The FMPC site includes a plant designed for the reduction of uranium hexafluoride (UF 6 ) to uranium tetrafluoride (UF 4 ). Limited operation of the upgraded reduction facility began in August 1984 and continued through January 19, 1986. A reaction vessel ruptured on that date causing the plant operation to be shut down. The DOE conducted a Class B investigation with the findings of the investigation board issued in preliminary form in May 1986 and as a final recommendation in July 1986. A two-phase restart of the plant was planned and implemented. Phase I included implementing safety system modifications, changing reaction vessel temperature control strategy, and operating the reduction plant under an 8-week controlled test. The results of the test period are the subject of this report. 41 figs., 11 tabs

  13. Partial degradation of five pesticides and an industrial pollutant by ozonation in a pilot-plant scale reactor

    International Nuclear Information System (INIS)

    Maldonado, M.I.; Malato, S.; Perez-Estrada, L.A.; Gernjak, W.; Oller, I.; Domenech, Xavier; Peral, Jose

    2006-01-01

    Aqueous solutions of a mixture of several pesticides (alachlor, atrazine, chlorfenvinphos, diuron and isoproturon), considered PS (priority substances) by the European Commission, and an intermediate product of the pharmaceutical industry (α-methylphenylglycine, MPG) chosen as a model industrial pollutant, have been degraded at pilot-plant scale using ozonation. This study is part of a large research project [CADOX Project, A Coupled Advanced Oxidation-Biological Process for Recycling of Industrial Wastewater Containing Persistent Organic Contaminants, Contract No.: EVK1-CT-2002-00122, European Commission, http://www.psa.es/webeng/projects/cadox/index.html[1

  14. Partial degradation of five pesticides and an industrial pollutant by ozonation in a pilot-plant scale reactor

    Energy Technology Data Exchange (ETDEWEB)

    Maldonado, M.I. [PSA - Plataforma Solar de Almeria, CIEMAT, Crta Senes km 4, Tabernas, Almeria 04200 (Spain); Malato, S. [PSA - Plataforma Solar de Almeria, CIEMAT, Crta Senes km 4, Tabernas, Almeria 04200 (Spain); Perez-Estrada, L.A. [PSA - Plataforma Solar de Almeria, CIEMAT, Crta Senes km 4, Tabernas, Almeria 04200 (Spain); Gernjak, W. [PSA -Plataforma Solar de Almeria, CIEMAT, Crta Senes km 4, Tabernas, Almeria 04200 (Spain); Oller, I. [PSA - Plataforma Solar de Almeria, CIEMAT, Crta Senes km 4, Tabernas, Almeria 04200 (Spain); Domenech, Xavier [Departament de Quimica, Edifici Cn, Universitat Autonoma de Barcelona, E-08193 Bellaterra, Barcelona (Spain); Peral, Jose [Departament de Quimica, Edifici Cn, Universitat Autonoma de Barcelona, E-08193 Bellaterra, Barcelona (Spain)]. E-mail: jose.peral@uab.es

    2006-11-16

    Aqueous solutions of a mixture of several pesticides (alachlor, atrazine, chlorfenvinphos, diuron and isoproturon), considered PS (priority substances) by the European Commission, and an intermediate product of the pharmaceutical industry ({alpha}-methylphenylglycine, MPG) chosen as a model industrial pollutant, have been degraded at pilot-plant scale using ozonation. This study is part of a large research project [CADOX Project, A Coupled Advanced Oxidation-Biological Process for Recycling of Industrial Wastewater Containing Persistent Organic Contaminants, Contract No.: EVK1-CT-2002-00122, European Commission, http://www.psa.es/webeng/projects/cadox/index.html[1

  15. Plant life management and modernisation: Research challenges in the EU

    International Nuclear Information System (INIS)

    Rintamaa, R.; Aho-Mantila, I.

    2011-01-01

    -wide coordinated research strategy for plant life integrity management and long-term operation has been defined. Mapping exercise of expertises performed under NULIFE confirmed that NULIFE R and D resources are versatile and high quality. In addition to the wide range of technical expertise available, these are widely spread at geographical and organizational level. Four expert groups, with identified members and links to national programmes, have now produced state-of-the-art type reports related to their expertises. Stress corrosion cracking and thermal fatigue pilot projects have finished concluding reports. Several project proposals have been introduced and optimised for new NULIFE pilot projects or other R and D projects. Based on NULIFE business plan, the discussion of long-term business plan, operational model and statute of the future NULIFE institute has been started. NULIFE maintains the sustainability of nuclear power by focusing on the continued, 60+ years of safe operation of nuclear power plants.

  16. Safety study on nuclear heat utilization system - accident delineation and assessment on nuclear steelmaking pilot plant

    International Nuclear Information System (INIS)

    Yoshida, T.; Mizuno, M.; Tsuruoka, K.

    1982-01-01

    This paper presents accident delineation and assessment on a nuclear steelmaking pilot plant as an example of nuclear heat utilization systems. The reactor thermal energy from VHTR is transported to externally located chemical process plant employing helium-heated steam reformer by an intermediate heat transport loop. This paper on the nuclear steelmaking pilot plant will describe (1) system transients under accident conditions, (2) impact of explosion and fire on the nuclear reactor and the public and (3) radiation exposure on the public. The results presented in this paper will contribute considerably to understanding safety features of nuclear heat utilization system that employs the intermediate heat transport loop and the helium-heated steam reformer

  17. Application of neutron radiography to plant research

    International Nuclear Information System (INIS)

    Nakanishi, Tomoko

    1995-01-01

    Neutron radiography was used to image plant roots in soils. Soybeans were used as experimental plants. When the length of the soybean root was 3-5 cm, the plant was transferred to an alminum foil and cultivated by adding polyvinyl alcoholic polymer (polymer A) and pulm-derived polymer (polymer B) as water absorbing polymers to soils. Plant samples were removed sequentially and irradiated with neutrons for 19 seconds at the JRR-3M neutron radiography facility. After irradiation, X-ray film images were obtained to observe water dynamics of roots and soils. Neutron images of soybean roots showed that secondary roots had grown on the side of water absorbing polymer-added soils in the case of polymer A, but on the side of non-added soils in the case of polymer B. When polymer B was added just below the soils where roots were grown, root growth was restricted only to the soil surface, and plant growth condition and dry weight were similar to those in the control plants. Thus the design of root shape may be possible by using polymer B. Similar experiment was made on 5 kinds of trees. Images of cross section of Japanese Cypress revealed that water contained in the tree is not always present along with growth ring of the tree. These findings may have an important implication for the potential application of neutron radiography in plant research. (N.K.)

  18. Examining mathematics attitude in a TIMSS 2003 pilot research

    Directory of Open Access Journals (Sweden)

    Kadijević Đorđe M.

    2003-01-01

    Full Text Available Apart from the data on test reliability, the psychometric features of the TIMSS variables are not officially available. It is therefore not clear whether the TIMSS findings capture real educational trends. Being concerned with mathematics attitude, the aim of this research was to determine the psychometric values of a mathematics attitude scale derived from a student questionnaire, and, if these are appropriate, to examine the relation of mathematics attitude to gender and mathematics achievement, and search for gender differences in the applied mathematics attitude indicators. By using a sample of 89 seventh-grade students involved in a TIMSS 2003 pilot research, it revealed the following findings: (a the representativity reliability, homogeneity and validity of the applied attitude scale were acceptable, (b attitude to mathematics was related to mathematics achievement, (c gender differences in mathematics attitude were not found and (d gender differences in the applied indicators were only present for the statement "I need to do well in mathematics to get into the faculty of my choice" where males expressed a higher agreement than females.

  19. Pilot program to identify valve failures which impact the safety and operation of light water nuclear power plants

    International Nuclear Information System (INIS)

    Tsacoyeanes, J.C.; Raju, P.P.

    1980-04-01

    The pilot program described has been initiated under the Department of Energy Light Water Reactor Safety Research and Development Program and has the following specific objectives: to identify the principal types and causes of failures in valves, valve operators and their controls and associated hardware, which lead to, or could lead to plant trip; and to suggest possible remedies for the prevention of these failures and recommend future research and development programs which could lead to minimizing these valve failures or mitigating their effect on plant operation. The data surveyed cover incidents reported over the six-year period, beginning 1973 through the end of 1978. Three sources of information on valve failures have been consulted: failure data centers, participating organizations in the nuclear power industry, and technical documents

  20. Applications of pilot scanning behavior to integrated display research

    Science.gov (United States)

    Waller, M. C.

    1977-01-01

    The oculometer is an electrooptical device designed to measure pilot scanning behavior during instrument approaches and landing operations. An overview of some results from a simulation study is presented to illustrate how information from the oculometer installed in a visual motion simulator, combined with measures of performance and control input data, can provide insight into the behavior and tactics of individual pilots during instrument approaches. Differences in measured behavior of the pilot subjects are pointed out; these differences become apparent in the way the pilots distribute their visual attention, in the amount of control activity, and in selected performance measures. Some of these measured differences have diagnostic implications, suggesting the use of the oculometer along with performance measures as a pilot training tool.

  1. A Practical Approach for Studying Fouling Process in Li-Recovery Pilot Plant

    Science.gov (United States)

    Kong, M.; Yoon, H.; Eom, C.; Kim, B.; Chung, K.

    2011-12-01

    The efficiency of selective ion recovery such as lithium from seawater has been major interest of previous studies. However, the characterization of adsorption behavior as well as dissolution yield as discharging environmentally problematic chemical species must carefully studied in various conditions including different seawater conditions [1]. Marine biofouling communities are complex, highly dynamic ecosystems consisting of a diverse range of organisms. The development of such communities begins with bacterial attachment followed by the colonization of higher organisms such as invertebrate larvae and algal spores [2-3]. Monitoring and field studies regarding fouling problems during operation of Li-recovery pilot plant which is designed by the Korea Institute of Geoscience & Mineral Resources (KIGAM) were major concern of this study. We examined fouling process for the duration of exposure time in real marine environment. Substrated with no-antifouling treated material and antifouling treated material were exposed and tested for different behaviors toward fouling in ocean. SEM-EDS (Scanning Electron Microscope-Energy dispersive Spectroscopy) analysis was done for surface identification of specific elements for possible dissolution during seawater exposure. To identify organic compound was used GC-MS (Gas Chromatography Mass Spectrometer) analysis. Experiment results, organisms such as alga are fouled the most on 30 days and antitreated material is fouled less than non antitreated material. Operating Li-recovery pilot plant to sea, we need to consider in order to effectively and economically resolve the fouling problem. Acknowledgement : This research was supported by the national research project titled "The Development of Technology for Extraction of Resources Dissolved in Seawater" of the Korea Institute of Geoscience and Mineral Resources (KIGAM) funded by the Ministry of Land, Transport and Maritime Affairs. References [1] M. Y. Diego, K. Soren, and D. J. Kim

  2. Pilot project concerning the establishment of a collective biomass conversion plant on the island of Mors

    International Nuclear Information System (INIS)

    1993-06-01

    This pilot project comprises a feasibility study in connection with plans to establish a biomass conversion plant, on the Danish island of Mors, which would provide methane to be used as fuel, in combination with natural gas, for a cogeneration plant serving six villages. The subjects of location, organization, the transportation of biomass, the design of the biomass conversion plant, economical aspects and conditions of the use of the methane are discussed as a basis for decisions in this respect. Environmental considerations are also dealt with. (AB)

  3. Genomics-based plant germplasm research (GPGR)

    Institute of Scientific and Technical Information of China (English)

    Jizeng Jia; Hongjie Li; Xueyong Zhang; Zichao Li; Lijuan Qiu

    2017-01-01

    Plant germplasm underpins much of crop genetic improvement. Millions of germplasm accessions have been collected and conserved ex situ and/or in situ, and the major challenge is now how to exploit and utilize this abundant resource. Genomics-based plant germplasm research (GPGR) or "Genoplasmics" is a novel cross-disciplinary research field that seeks to apply the principles and techniques of genomics to germplasm research. We describe in this paper the concept, strategy, and approach behind GPGR, and summarize current progress in the areas of the definition and construction of core collections, enhancement of germplasm with core collections, and gene discovery from core collections. GPGR is opening a new era in germplasm research. The contribution, progress and achievements of GPGR in the future are predicted.

  4. Trends in plant research using molecular markers.

    Science.gov (United States)

    Garrido-Cardenas, Jose Antonio; Mesa-Valle, Concepción; Manzano-Agugliaro, Francisco

    2018-03-01

    A deep bibliometric analysis has been carried out, obtaining valuable parameters that facilitate the understanding around the research in plant using molecular markers. The evolution of the improvement in the field of agronomy is fundamental for its adaptation to the new exigencies that the current world context raises. In addition, within these improvements, this article focuses on those related to the biotechnology sector. More specifically, the use of DNA markers that allow the researcher to know the set of genes associated with a particular quantitative trait or QTL. The use of molecular markers is widely extended, including: restriction fragment length polymorphism, random-amplified polymorphic DNA, amplified fragment length polymorphism, microsatellites, and single-nucleotide polymorphisms. In addition to classical methodology, new approaches based on the next generation sequencing are proving to be fundamental. In this article, a historical review of the molecular markers traditionally used in plants, since its birth and how the new molecular tools facilitate the work of plant breeders is carried out. The evolution of the most studied cultures from the point of view of molecular markers is also reviewed and other parameters whose prior knowledge can facilitate the approach of researchers to this field of research are analyzed. The bibliometric analysis of molecular markers in plants shows that top five countries in this research are: US, China, India, France, and Germany, and from 2013, this research is led by China. On the other hand, the basic research using Arabidopsis is deeper in France and Germany, while other countries focused its efforts in their main crops as the US for wheat or maize, while China and India for wheat and rice.

  5. Nuclear Plant Aging Research (NPAR) program plan

    International Nuclear Information System (INIS)

    1991-06-01

    A comprehensive Nuclear Plant Aging Research (NPAR) Program was implemented by the US NRC office of Nuclear Regulatory Research in 1985 to identify and resolve technical safety issues related to the aging of systems, structures, and components in operating nuclear power plants. This is Revision 2 to the Nuclear Plant Aging Research Program Plant. This planes defines the goals of the program the current status of research, and summarizes utilization of the research results in the regulatory process. The plan also describes major milestones and schedules for coordinating research within the agency and with organizations and institutions outside the agency, both domestic and foreign. Currently the NPAR Program comprises seven major areas: (1) hardware-oriented engineering research involving components and structures; (2) system-oriented aging interaction studies; (3) development of technical bases for license renewal rulemaking; (4) determining risk significance of aging phenomena; (5) development of technical bases for resolving generic safety issues; (6) recommendations for field inspection and maintenance addressing aging concerns; (7) and residual lifetime evaluations of major LWR components and structures. The NPAR technical database comprises approximately 100 NUREG/CR reports by June 1991, plus numerous published papers and proceedings that offer regulators and industry important insights to aging characteristics and aging management of safety-related equipment. Regulatory applications include revisions to and development of regulatory guides and technical specifications; support to resolve generic safety issues; development of codes and standards; evaluation of diagnostic techniques; (e.g., for cables and valves); and technical support for development of the license renewal rule. 80 refs., 25 figs., 10 tabs

  6. Progress in Developing a High-Availability Advanced Tokamak Pilot Plant

    Energy Technology Data Exchange (ETDEWEB)

    Brown, T.; Goldston, R.; Kessel, C.; Neilson, G.; Menard, J.; Prager, S.; Scott, S.; Titus, P.; Zarnstorff, M., E-mail: tbrown@pppl.gov [Princeton University, Princeton Plasma Physics Laboratory, Princeton (United States); Costley, A. [Henley on Thames (United Kingdom); El-Guebaly, L. [University of Wisconsin, Madison (United States); Malang, S. [Fusion Nuclear Technology Consulting, Linkenheim (Germany); Waganer, L. [St. Louis (United States)

    2012-09-15

    Full text: A fusion pilot plant study was initiated to clarify the development needs in moving from ITER to a first of a kind fusion power plant, following a path similar to the approach adopted for the commercialization of fission. The mission of the pilot plant was set to encompass component test and fusion nuclear science missions yet produce net electricity with high availability in a device designed to be prototypical of the commercial device. The objective of the study was to evaluate three different magnetic configuration options, the advanced tokamak (AT), spherical tokamak (ST) and compact stellarator (CS) in an effort to establish component characteristics, maintenance features and the general arrangement of each candidate device. With the move to look beyond ITER the fusion community is now beginning to embark on DEMO reactor studies with an emphasis on defining configuration arrangements that can meet a high availability goal. In this paper the AT pilot plant design will be presented. The selected maintenance approach, the device arrangement and sizing of the in-vessel components and details of interfacing auxiliary systems and services that impact the ability to achieve high availability operations will be discussed. Efforts made to enhance the interaction of in-vessel maintenance activities, the hot cell and the transfer process to develop simplifying solutions will also be addressed. (author)

  7. Sequential Design of Experiments to Maximize Learning from Carbon Capture Pilot Plant Testing

    Energy Technology Data Exchange (ETDEWEB)

    Soepyan, Frits B.; Morgan, Joshua C.; Omell, Benjamin P.; Zamarripa-Perez, Miguel A.; Matuszewski, Michael S.; Miller, David C.

    2018-02-06

    Pilot plant test campaigns can be expensive and time-consuming. Therefore, it is of interest to maximize the amount of learning and the efficiency of the test campaign given the limited number of experiments that can be conducted. This work investigates the use of sequential design of experiments (SDOE) to overcome these challenges by demonstrating its usefulness for a recent solvent-based CO2 capture plant test campaign. Unlike traditional design of experiments methods, SDOE regularly uses information from ongoing experiments to determine the optimum locations in the design space for subsequent runs within the same experiment. However, there are challenges that need to be addressed, including reducing the high computational burden to efficiently update the model, and the need to incorporate the methodology into a computational tool. We address these challenges by applying SDOE in combination with a software tool, the Framework for Optimization, Quantification of Uncertainty and Surrogates (FOQUS) (Miller et al., 2014a, 2016, 2017). The results of applying SDOE on a pilot plant test campaign for CO2 capture suggests that relative to traditional design of experiments methods, SDOE can more effectively reduce the uncertainty of the model, thus decreasing technical risk. Future work includes integrating SDOE into FOQUS and using SDOE to support additional large-scale pilot plant test campaigns.

  8. Demonstration test of electron beam flue gas treatment pilot plant of a coal fired thermal power station

    International Nuclear Information System (INIS)

    Doi, Yoshitaka; Hayashi, Kazuaki; Izutsu, Masahiro; Watanabe, Shigeharu; Namba, Hideki; Tokunaga, Okihiro; Hashimoto, Shoji; Tanaka, Tadashi; Ogura, Yoshimi.

    1995-01-01

    The Japan Atomic Energy Research Institute, Chubu Electric Power Company and Ebara Corporation jointly constructed a pilot plant for electron beam flue gas treatment (dry process) capable of treating 12,000 m 3 /h (NTP) of flue gas from a coal fired boiler, at Shin-Nagoya Thermal Power Station, Chubu Electric Power Company. Various tests carried out at the plant over a period extending one year verified the followings. By appropriately controlling parameters such as electron beam dosage, flue gas temperature, and ammonia stoichiometric amount, highly efficient simultaneous SO 2 and NOx removal from flue gas was achieved under all gas conditions, equal to or more efficient than that by the highest level conventional treatment. The operation of the pilot plant was stable and trouble-free over a long term, and the operation and the process was easy to operate and control. By-products (ammonium sulfate and ammonium nitrate) produced by the flue gas treatment were proven to have superior quality, equivalent to that of market-available nitrogen fertilizers. These by-products had been registered as by-product nitrogen fertilizers. (author)

  9. Irradiation pilot plants and experimental facilities available for food preservation

    International Nuclear Information System (INIS)

    1975-01-01

    With the ever-increasing world food crisis mankind has to face today, the prevention of spoilage of perishable food is gaining in momentum. The World Food Conference (Rome, November 1974) of the United Nations clearly recognized the importance of food preservation and urged action in this field. Irradiation is one of the recently discovered methods to preserve food. Its practical introduction largely depends on three main factors: (a) proof of the safety for human consumption of the irradiated product, (b) technological feasibility and (c) economic competitiveness of the process. As data on safety for consumption ('wholesomeness') continue to become available, the number of countries authorizing the irradiation of certain food items is growing (present total: 17 countries), and the same is true for the number of licensed irradiated commodities (total: 23). Under these conditions, testing of the technological and economic feasibility of food irradiation is a matter of increasing importance. Economic feasibility of any industrial operation can only be studied in larger-scale experiments. Thus, they can only be performed with radiation sources larger than those found in laboratories, i.e. in pilot irradiators, capable of handling from a few hundred to a few thousand kilograms of material within a short period of time. The Food Preservation Section of the Joint FAO/IAEA Division of Atomic Energy in Food and Agriculture has attempted to collect data on the availability, for food preservation, of suitable irradiators in Member States

  10. The pilot plant experiment of electron beam irradiation process for removal of NOx and SOx from sinter plant exhaust gas in the iron and steel industry

    International Nuclear Information System (INIS)

    Kawamura, K.; Katayama, T.; Kawamura, Ke.

    1981-01-01

    Air pollution problem has become more important in the progress of industry. Nitrogen oxides (NOx, mostly NO) and sulfur oxides (SOx, mostly SO 2 ) which are contained in a sinter plant exhaust gas, are known as serious air pollutants. In such circumstances, an attempt has been made to simultaneously remove NOx and SOx from the sinter plant exhaust gas by means of a new electron beam irradiation process. The process consists of adding a small amount of NH 3 to the exhaust gas, irradiating the gas by electron beam, forming ammonium salts by reactions of NOx and SOx with the NH 3 and collecting ammonium salts by dry electrostatic precipitator (E.P.). Basic research on the present process had been performed using heavy oil combustion gas. Based on the results research was launched to study the applicability of the process to the treatment of sinter plant exhaust gas. A pilot plant, capable of treating a gas flow of 3000 Nm 3 /H was set up, and experiments were performed from July 1977 to June 1978. The plant is described and the results are presented. (author)

  11. Socioeconomic study for the proposed waste isolation pilot plant

    Energy Technology Data Exchange (ETDEWEB)

    1980-10-01

    This document presents the historical and existing socioeconomic conditions in the vicinity of the proposed plant, projected changes in those conditions with and without the plant, and an outline of the various techniques used to make these projections. The analysis predicts impacts on the general economy in the area near the plant and on employment, personal income, population, social structure, the private economic sector, housing, land use, community services and facilities, and local government finances. Among the most important results are the following predictions: The economy of the area will derive $165 million directly and indirectly during the first 7.5 years of the project. After that, it will derive about $21 million directly and indirectly during each year of full operation. About 2100 jobs will be created directly and indirectly at the peak of the construction and about 950 jobs during the full operation. A net in-migration will occur: about 2250 people at the peak of the construction and about 1000 people during operation. A housing shortage may begin in Carlsbad in 1981 or 1982 and last for about 2 years.

  12. Socioeconomic study for the proposed waste isolation pilot plant

    International Nuclear Information System (INIS)

    1980-10-01

    This document presents the historical and existing socioeconomic conditions in the vicinity of the proposed plant, projected changes in those conditions with and without the plant, and an outline of the various techniques used to make these projections. The analysis predicts impacts on the general economy in the area near the plant and on employment, personal income, population, social structure, the private economic sector, housing, land use, community services and facilities, and local government finances. Among the most important results are the following predictions: The economy of the area will derive $165 million directly and indirectly during the first 7.5 years of the project. After that, it will derive about $21 million directly and indirectly during each year of full operation. About 2100 jobs will be created directly and indirectly at the peak of the construction and about 950 jobs during the full operation. A net in-migration will occur: about 2250 people at the peak of the construction and about 1000 people during operation. A housing shortage may begin in Carlsbad in 1981 or 1982 and last for about 2 years

  13. Space shuttle pilot-induced-oscillation research testing

    Science.gov (United States)

    Powers, B. G.

    1984-01-01

    The simulation requirements for investigation of pilot-induced-oscillation (PIO) characteristics during the landing phase are discussed. Orbiters simulations and F-8 digital fly-by-wire aircraft tests are addressed.

  14. Two treatment methods for stormwater sediments--pilot plant and landfarming--and reuse of the treated sediments in civil engineering.

    Science.gov (United States)

    Petavy, F; Ruban, V; Conil, P; Viau, J Y; Auriol, J C

    2009-07-01

    The aim of this research was to present a pilot plant for the treatment of stormwater sediments and to compare the decontamination rate to that obtained by landfarming. The possibilities for reuse of the treated sediments in civil engineering are also studied. Four sediments from retention/infiltration ponds or from street sweeping were studied. In each case organic matter (OM), total hydrocarbons (TH) and polycyclic aromatic hydrocarbons (PAH) were measured. Geotechnical tests were carried out to evaluate the reuse possibilities of the treated sediments. Treatment by means of the pilot plant was efficient at reducing TH and PAH concentrations: THs were reduced by 53-97% and PAHs were decreased by 60-95%. By comparison, a reduction of 45-75% in TH concentration is obtained with landfarming, whereas there is no significant decrease in PAHs. Furthermore, geotechnical tests showed that the treated fractions from the pilot plant can be reused as road embankments and as a capping layer. These results are most encouraging and show that stormwater sediments can valuably be reused after treatment in a pilot plant. Landfarming is less efficient but this technique could be used as a pretreatment in the case of high TH pollution.

  15. Deep geologic disposal of mixed waste in bedded salt: The Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    Rempe, N.T.

    1993-01-01

    Mixed waste (i.e., waste that contains both chemically hazardous and radioactive components) poses a moral, political, and technical challenge to present and future generations. But an international consensus is emerging that harmful byproducts and residues can be permanently isolated from the biosphere in a safe and environmentally responsible manner by deep geologic disposal. To investigate and demonstrate such disposal for transuranic mixed waste, derived from defense-related activities, the US Department of Energy has prepared the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico. This research and development facility was excavated approximately at the center of a 600 m thick sequence of salt (halite) beds, 655 m below the surface. Proof of the long-term tectonic and hydrological stability of the region is supplied by the fact that these salt beds have remained essentially undisturbed since they were deposited during the Late Permian age, approximately 225 million years ago. Plutonium-239, the main radioactive component of transuranic mixed waste, has a half-life of 24,500 years. Even ten half-lives of this isotope - amounting to about a quarter million years, the time during which its activity will decline to background level represent only 0.11 percent of the history of the repository medium. Therefore, deep geologic disposal of transuranic mixed waste in Permian bedded salt appears eminently feasible

  16. Basic data report for drillhole WIPP 11 (Waste Isolation Pilot Plant - WIPP)

    International Nuclear Information System (INIS)

    1982-02-01

    Seismic reflection data from petroleum industry sources showed anomalous reflectors in the Castile Formation over a small area about 3 miles north of the center of the Waste Isolation Pilot Plant (WIPP) site. Additional corroborative seismic reflection data were collected as part of WIPP investigations, and WIPP 11 was drilled to investigate the anomaly. WIPP 11 was drilled near the northwest corner of Section 9, T.22.S., R.31E. it penetrated, in descending order, sand dune deposits and the Gatuna Formation (29'), Santa Rosa Sandstone (132'), Dewey Lake Red Beds (502'), Rustler Formation (288'), Salado Formation (1379'), and most of the Castile Formation (1240'). Beds within the lower part of the Salado, and the upper anhydrite of the Castile, are thinner than normal; these beds are displaced upward structurally by the upper Castile halite which is highly thickened (about 968'). The lowest halite is thin (51') and the basal anhydrite was not completely penetrated. Subsequent seismic and borehole data has shown WIPP 11 to be in a structural complex now identified as the disturbed zone. The WIPP is a demonstration facility for the disposal of transuranic (TRU) waste from defense programs. The WIPP will also provide a research facility to investigate the interactions between bedded salt and high level waste, though there are no plans at this time to dispose of high level waste or spent fuel at WIPP

  17. Annual site environmental monitoring report for the Waste Isolation Pilot Plant, Calendar year 1985

    International Nuclear Information System (INIS)

    Reith, C.; Prince, K.; Fischer, T.; Rodriguez, A.; Uhland, D.; Winstanley, D.

    1986-04-01

    This is the first Annual Site Environmental Monitoring Report for the Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico. The WIPP project is operated by the US Department of Energy (DOE) for the purpose of providing a research and development facility to demonstrate the safe disposal of radioactive wastes generated by the defense activities of the U.S. Government. The report provides a comprehensive description of environmental activities at WIPP during Calendar Year 1985, including: a description of the WIPP project and its mission; a description of the local environment, including demographics; a summary of environmental program information, including an update on the status of environmental permits and compliance activities; a presentation of the findings of the Radiological Baseline Program (RBP), which is a program to characterize radionuclide activities in the environment around the WIPP site; and a summary of findings of the Ecological Monitoring Program (EMP), which examines non-radiological impacts of WIPP construction on the surrounding ecosystem. The WIPP facility is under construction, and will not receive radioactive wastes before October 1988. Therefore, this report describes the status of preoperational (as opposed to operational) environmental activities. 29 refs., 17 figs., 22 tabs

  18. Draft plan for the Waste Isolation Pilot Plant test phase: Performance assessment and operations demonstration

    International Nuclear Information System (INIS)

    1989-04-01

    The mission of the Waste Isolation Pilot Plant (WIPP) Project is to provide a research and development facility to demonstrate the safe disposal of transuranic (TRU) radioactive wastes resulting from United States defense programs. With the Construction Phase of the WIPP facility nearing completion, WIPP is ready to initiate the next phase in its development, the Test Phase. The purpose of the Test Phase is to collect the necessary scientific and operational data to support a determination whether to proceed to the Disposal Phase and thereby designate WIPP a demonstration facility for the disposal of TRU wastes. This decision to proceed to the Disposal Phase is scheduled for consideration by September 1994. Development of the WIPP facility is the responsibility of the United States Department of Energy (DOE), whose Albuquerque Operations Office has designated the WIPP Project Office as Project Manager. This document describes the two major programs to be conducted during the Test Phase of WIPP: (1) Performance Assessment for determination of compliance with the Environmental Protection Agency Standard and (2) Operations Demonstration for evaluation of the safety and effectiveness of the DOE TRU waste management system's ability to emplace design throughput quantities of TRU waste in the WIPP facility. 42 refs., 38 figs., 14 tabs

  19. Historical Background on Assessingt the Performance of the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    Rechard, R.P.

    1999-01-01

    In 1979, six years after selecting the Delaware Basin as a potential disposal area, Congress authorized the US Department of Energy to build the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico, as a research and development facility for the safe management, storage, and disposal of waste contaminated with transuranic radioisotopes. In 1998, 19 years after authorization and 25 years after site selection, the US Environmental Protection Agency (EPA) certified that the WIPP disposal system complied with its regulations. The EPA's decision was primarily based on the results from a performance assessment conducted in 1996. This performance assessment was the culmination of four preliminary performance assessments conducted between 1989 and 1992. This report provides a historical setting and context for how the performance of the deep geologic repository at the WIPP was analyzed. Also included is background on political forces acting on the project. For example, the federal requirement to provide environmental impact statements and negotiated agreements with the State of New Mexico influenced the type of scientific areas that were investigated and the engineering analysis prior to 1989 for the WIPP

  20. Historical Background on Assessment the Performance of the Waste Isolation Pilot Plant

    Energy Technology Data Exchange (ETDEWEB)

    Rechard, R.P.

    1999-06-01

    In 1979, six years after selecting the Delaware Basin as a potential disposal area, Congress authorized the US Department of Energy to build the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico, as a research and development facility for the safe management, storage, and disposal of waste contaminated with transuranic radioisotopes. In 1998, 19 years after authorization and 25 years after site selection, the US Environmental Protection Agency (EPA) certified that the WIPP disposal system complied with its regulations. The EPA's decision was primarily based on the results from a performance assessment conducted in 1996. This performance assessment was the culmination of four preliminary performance assessments conducted between 1989 and 1992. This report provides a historical setting and context for how the performance of the deep geologic repository at the WIPP was analyzed. Also included is background on political forces acting on the project. For example, the federal requirement to provide environmental impact statements and negotiated agreements with the State of New Mexico influenced the type of scientific areas that were investigated and the engineering analysis prior to 1989 for the WIPP.

  1. Notice of intent to discharge water contaminants. Waste Isolation Pilot Plant, Eddy County, NM

    International Nuclear Information System (INIS)

    Hart, J.S.; Porter, K.R.; Register, J.K.

    1983-04-01

    This report provides information in support of a ''Notice of Intent to Discharge Water Contaminants,'' pursuant to Section 1-201 of the New Mexico Water Quality Control Commission Regulations. The anticipated discharges are not expected to move directly or indirectly into groundwater. These discharges will be caused by activities related to the construction of the Waste Isolation Pilot Plant (WIPP), a US Department of Energy (DOE) research and development program to demonstrate the safe disposal of radioactive wastes resulting from defense activities and programs of the United States. The facility is to be developed in deep layers of bedded salt. The WIPP site is located in Eddy County, New Mexico, about 26 miles east of Carlsbad. The US Department of Energy, WIPP Project Office, Albuquerque, New Mexico, as the sponsor of the project, is responsible for any discharges from the site. The following sections describe generally the WIPP construction activities. Pertinent site conditions, potential sources of discharges and their expected effects, and proposed groundwater monitoring efforts are also described

  2. Optimization of instant powdered chicken feet broth’s drying temperature and time on pilot plant scale production

    Science.gov (United States)

    Hidayati, N.; Widyaningsih, T. D.

    2018-03-01

    Chicken feet by-product of chicken industries amounted to approximately 65,894 tons/year commonly used as broths. These by-products are potentially produced into an instant form as an anti-inflammatory functional food on industrial scale. Therefore, it is necessary to optimize the critical parameters of the drying process. The aim of this study was to determine the optimum temperature and time of instant powdered chicken feet broth’s drying on pilot plant scale, to find out product’s comparison of the laboratory and pilot plant scale, and to assess financial feasibility of the business plan. The optimization of pilot plant scale’s research prepared and designed with Response Surface Methodology-Central Composite Design. The optimized factors were powdered broth’s drying temperature (55°C, 60°C, 65°C) and time (10 minutes, 11 minutes, 12 minutes) with the response observed were water and chondroitin sulphate content. The optimum condition obtained was drying process with temperature of 60.85°C for 10,05 minutes resulting in 1.90 ± 0.02% moisture content, 32.48 ± 0.28% protein content, 12.05 ± 0.80% fat content, 28.92 ± 0.09 % ash content, 24.64 ± 0.52% carbohydrate content, 1.26 ± 0.05% glucosamine content, 0.99 ± 0.23% chondroitin sulphate content, 50.87 ± 1.00% solubility, 8.59 ± 0.19% water vapour absorption, 0.37% levels of free fatty acid, 13.66 ± 4.49% peroxide number, lightness of 60.33 ± 1.24, yellowness of 3.83 ± 0.26 and redness of 21.77 ± 0.42. Financial analysis concluded that this business project was feasible to run.

  3. Development of pilot model of virtual nuclear power plant and its application to radiation management

    International Nuclear Information System (INIS)

    Kang, K. D.; Sin, S. W.

    2002-01-01

    Using Virtual Reality (VR) technique, a real model for radiation controlled area in nuclear power plant was developed and a feasibility study to develop a computational program to estimate radiation dose was performed. For this purpose a pilot model with an dynamic function and bi-directional communication was developed. This model was enhanced from the existing 3-D single-directional communication. In this pilot model, a plant visitor needs a series of security checking process initially. If he(she) enters the controlled area and approaches radiation hazard area, the alarms with warning lamp will be initiated automatically. Throughout the test to connect this model from both domestic and international sites in various time zones it has proven that it showed a sufficient performance. Therefore this model can be applied to broad fields as radiation protection procedures photographic data, on-line dose program

  4. Research directions in plant protection chemistry

    Directory of Open Access Journals (Sweden)

    Andras Szekacs

    2017-09-01

    Full Text Available This Opinion paper briefly summarizes the views of the authors on the directions of research in the area of plant protection chemistry. We believe these directions need to focus on (1 the discovery of new pesticide active ingredients, and (2 the protection of human health and the environment. Research revenues are discussed thematically in topics of target site identification, pesticide discovery, environmental aspects, as well as keeping track with the international trends. The most fundamental approach, target site identification, covers both computer-aided molecular design and research on biochemical mechanisms. The discovery of various classes of pesticides is reviewed including classes that hold promise to date, as well as up-to-date methods of innovation, e.g. utilization of plant metabolomics in identification of novel target sites of biological activity. Environmental and ecological aspects represent a component of increasing importance in pesticide development by emphasizing the need to improve methods of environmental analysis and assess ecotoxicological side-effects, but also set new directions for future research. Last, but not least, pesticide chemistry and biochemistry constitute an integral part in the assessment of related fields of plant protection, e.g. agricultural biotechnology, therefore, issues of pesticide chemistry related to the development and cultivation of genetically modified crops are also discussed.

  5. Interdisciplinary Research and Training Program in the Plant Sciences

    Energy Technology Data Exchange (ETDEWEB)

    Wolk, C.P.

    1992-01-01

    Research on plants continued. Topics include: Molecular basis of symbiotic plant-microbe interations; enzymatic mechanisms and regulation of plant cell wall biosynthesis; molecular mechanisms that regulate the expression of genes in plants; resistance of plants to environmental stress; studies on hormone biosynthesis and action; plant cell wall proteins; interaction of nuclear and organelle genomes; sensor transduction in plants; molecular mechanisms of trafficking in the plant cell; regulation of lipid metabolism; molecular bases of plant disease resistance mechanisms; biochemical and molecular aspects of plant pathogenesis; developmental biology of nitrogen-fixing cyanobacteria; environmental control of plant development and its relation to plant hormones.

  6. Fiscal 1997 report of the development of high efficiency waste power generation technology. No.2 volume. Pilot plant verification test; Kokoritsu haikibutsu hatsuden gijutsu kaihatsu (pilot plant jissho shiken). 1997 nendo hokokusho (daini bunsatsu)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-03-01

    As to a high efficiency waste power generation system using general waste as fuel, the details of the following were described: design/construction management and operational study of pilot plant, design/manufacture/construction of pilot plant, and study of an optimal total system. Concerning the construction management and operational study, the paper described the application for governmental/official inspection procedures and taking inspection, process management of pilot plant, site patrol, safety management, management of trial run of pilot plant, drawing-up of a verification test plan and test run, etc. Relating to the design/manufacture/construction of pilot plant, an outline of the pilot plant was described. The paper also stated points to be considered in design of furnace structure and boiler structure, points to be considered of the verification test, etc. As to the study of an optimal total system, the following were described: survey of waste gasification/slagging power generation technology, basic study on RDF production process, survey of trends of waste power generation technology in the U.S., etc. 52 refs., 149 figs., 121 tabs.

  7. Preoperational checkout of the remote-handled transuranic waste handling at the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    1987-09-01

    This plan describes the preoperational checkout for handling Remote-Handled Transuranic (RH-TRU) Wastes from their receipt at the Waste Isolation Pilot Plant (WIPP) to their emplacement underground. This plan identifies the handling operations to be performed, personnel groups responsible for executing these operations, and required equipment items. In addition, this plan describes the quality assurance that will be exercised throughout the checkout, and finally, it establishes criteria by which to measure the success of the checkout. 7 refs., 5 figs

  8. The Planning of a Small Pilot Plant for Development Work on Aqueous Reprocessing of Nuclear Fuels

    Energy Technology Data Exchange (ETDEWEB)

    Sjoeborg, T U; Haeffner, E; Hultgren, Aa

    1963-10-15

    A shielded volume (42 m{sup 3}) in the hot laboratory at Kjeller, Norway, has been used for the installation of a small pilot plant intended for studies on nuclear fuel reprocessing. During the first period of operation (1963) a plutonium separation method (the Silex process) developed at AB Atomenergi will be studied. This document is a description of the project during the stage of technical planning and chemical process development.

  9. Resource Conservation and Recovery Act Part B permit application [for the Waste Isolation Pilot Plant (WIPP)

    International Nuclear Information System (INIS)

    1993-01-01

    This volume contains Appendix D2, engineering design basis reports. Contents include: Design considerations for the waste hoist of the Waste Isolation Pilot Plant (WIPP); A site-specific study of wind and tornado probabilities at the WIPP Site in southeast New Mexico; Seismic evaluation report of underground facilities; and calculations for analysis of wind loads and tornado loads for WHB, seismic calculations, calculations for VOC-10 monitoring system, and for shaft at station A

  10. Enrichment of Macedonian lignite through briquetting. Demonstration pilot-plant

    International Nuclear Information System (INIS)

    Dimitrov, Konstantin; Kachurkov, Gjorgi; Popovski, Kiril; Armenski, Slave

    1998-01-01

    In 1997 for the first time the scientific institutes from Republic of Macedonia got the opportunity to take part in competition to realize the scientific-research activity, financed by European Union. In the area of energy it could be applied for programs TERMI and COPERNICUS. A research project is applied for the program INCO COPERNICUS 97, with participation of the following research institutes: Koppern Aufbereitungstechnik GMbH and Co.KG - Germany; ENTEGRO - Greek Company for Energy Technology - Greece; Mining Institute Skopje - Macedonia; Faculty of Mechanical Engineering, Skopje - Macedonia; Faculty of Technical Sciences, Bitola - Macedonia; Central Institute for work protection, Skopje - Macedonia; Faculty for Industrial Chemistry and Metallurgy - Bulgaria. This paper presents the aim of the research, expected results, methodology and distribution of work among the research institutes

  11. The starting up of a pilot plant for radioactive incinerator ash conditioning - results of two embedding campaigns

    International Nuclear Information System (INIS)

    Kertesz, C.J.; Chenavas, P.R.; Naud, G.M.

    1990-01-01

    A new pilot plant called 'PICC' designed for radioactive incinerator ash conditioning, by embedding in several matrices, was launched at the Nuclear Research Centre in Cadarache - France - in the middle of 1988. This polyvalent facility can work with the three following embedding products = cement, thermosetting epoxide resin and an epoxide-cement compound. The capacity per day of the plant is two 100 or 200 I drums of solidified ash form. Two embedding campaigns have been carried out on inactive ashes: the first is a cementation campaign, done on phosphated ash coming from incineration of spent tributylphosphate. The second is a polymer cement campaign done on simulated alpha ash coming from technological wastes. Description of the PICC and data on these two campaigns are given

  12. 2010 Plant Molecular Biology Gordon Research Conference

    Energy Technology Data Exchange (ETDEWEB)

    Michael Sussman

    2010-07-23

    The Plant Molecular Biology Conference has traditionally covered a breadth of exciting topics and the 2010 conference will continue in that tradition. Emerging concerns about food security have inspired a program with three main themes: (1) genomics, natural variation and breeding to understand adaptation and crop improvement, (2) hormonal cross talk, and (3) plant/microbe interactions. There are also sessions on epigenetics and proteomics/metabolomics. Thus this conference will bring together a range of disciplines, will foster the exchange of ideas and enable participants to learn of the latest developments and ideas in diverse areas of plant biology. The conference provides an excellent opportunity for individuals to discuss their research because additional speakers in each session will be selected from submitted abstracts. There will also be a poster session each day for a two-hour period prior to dinner. In particular, this conference plays a key role in enabling students and postdocs (the next generation of research leaders) to mingle with pioneers in multiple areas of plant science.

  13. 1974 conceptual design description of a bedded salt pilot plant in southeast New Mexico

    International Nuclear Information System (INIS)

    1977-06-01

    The policy of the United States Atomic Energy Commission is to take custody of all commercial high-level radioactive wastes and maintain control of them in perpetuity. This policy (Title 10, Code of Federal Regulations, Part 50, Appendix F) requires that the high-level wastes from nuclear fuels reprocessing plants be solidified within five years after reprocessing and then shipped to a federal repository within ten years after reprocessing. Ultimate disposal sites and/or methods have not yet been selected and are not expected to be ready when waste deliveries begin about 1983. Therefore, the AEC plans to build an interim storage facility, called Retrievable Surface Storage Facility (RSSF), to store and isolate the waste from man and his environment until the suitability of the permanent repository is demonstrated and public acceptance has been established. Meantime, the AEC is proceeding with the study and development of an ultimate disposal method. Bedded salt is being considered for ultimate waste disposal, and work is in progress to develop a Bedded Salt Pilot Plant to demonstrate its acceptability. The pilot plant will permit in situ verification of laboratory work on the interaction of heat and radioactivity of the waste with the salt and surroundings. One concept of such a pilot facility is described

  14. [Yield of starch extraction from plantain (Musa paradisiaca). Pilot plant study].

    Science.gov (United States)

    Flores-Gorosquera, Emigdia; García-Suárez, Francisco J; Flores-Huicochea, Emmanuel; Núñez-Santiago, María C; González-Soto, Rosalia A; Bello-Pérez, Luis A

    2004-01-01

    In México, the banana (Musa paradisiaca) is cooked (boiling or deep frying) before being eaten, but the consumption is not very popular and a big quantity of the product is lost after harvesting. The unripe plantain has a high level of starch and due to this the use of banana can be diversified as raw material for starch isolation. The objective of this work was to study the starch yield at pilot plant scale. Experiments at laboratory scale were carried out using the pulp with citric acid to 0,3 % (antioxidant), in order to evaluate the different unitary operations of the process. The starch yield, based on starch presence in the pulp that can be isolated, were between 76 and 86 %, and the values at pilot plant scale were between 63 and 71 %, in different lots of banana fruit. Starch yield values were similar among the diverse lots, showing that the process is reproducible. The lower values of starch recovery at pilot plant scale are due to the loss during sieving operations; however, the amount of starch recovery is good.

  15. Research and development in power plant engineering

    International Nuclear Information System (INIS)

    Riedle, K.; Taud, R.

    2001-01-01

    Research and development are a bridge for visions that are escorted to a successful market introduction. Also in power plant engineering, research and development are a lever with which the product power plant, its technology and processes can be adapted to the quickly changing future market. In the overview given by this paper, therefore at first the development boosters and targets are outlined from the viewpoint of the market; then the available technology portfolio is addressed in a concise way. Targets for the development can be seen from the support programmes of the governments. Before a preview is given, some development topics from the point of view of the manufacturer are introduced. (orig.) [de

  16. Future-oriented computerized information system for power plant process control in a pilot project at Philippsburg nuclear power plant

    International Nuclear Information System (INIS)

    Woehrle, G.; Kraft, M.

    1988-01-01

    The motivation for the pilot project at Philippsburg nuclear power plant resulted from the Three Mile Island accident in 1979. The primary task embraces an efficient computer-aided reduction of information when a fault occurs based on a process engineering analysis of the information accrued. Accompanying this are a consolidation and evaluation of the information available in the control room. In this pilot project the new tasks of status monitoring, information reduction and operationalcontrol have been realized for the first time using a computer-aided process information system. In addition to the existing control computer, an information computer with approximately 1200 analogue and about 10000 binary signals has been installed. The installation of the system was completed in 1984 and in the meantime initial operational experience has become available. (orig.) [de

  17. Textile wastewater treatment and reuse by solar catalysis: results from a pilot plant in Tunisia.

    Science.gov (United States)

    Bousselmi, L; Geissen, S U; Schroeder, H

    2004-01-01

    Based on results from bench-scale flow-film-reactors (FFR) and aerated cascade photoreactors, a solar catalytic pilot plant has been built at the site of a textile factory. This plant has an illuminated surface area of 50 m2 and is designed for the treatment of 1 m3 h(-1) of wastewater. The preliminary results are presented and compared with a bench-scale FFR using textile wastewater and dichloroacetic acid. Equivalent degradation kinetics were obtained and it was demonstrated that the solar catalytic technology is able to remove recalcitrant compounds and color. However, on-site optimization is still necessary for wastewater reuse and for an economic application.

  18. Radiation treatment of sewage sludge - experience with an operating pilot plant

    International Nuclear Information System (INIS)

    Suess, A.; Lessel, T.

    1977-01-01

    After an operation time of a pilot plant for the γ-irradiation of sewage sludge after 3 years promising results could be obtained for economic considerations, killing rate of pathogenes and radiation induced changes in sedimentation properties. Irradiated sewage sludge indicated nearly the same effect on soil and plant as untreated. No special trained personnel are necessary for maintenance because of the simple design. Successful experience during 18 months resulted in an increase of the daily capacity up to 120 m 3 from December 1975. (author)

  19. Some economic considerations for a pilot plant based on the adsorber loop concept

    International Nuclear Information System (INIS)

    Koske, P.H.; Ohlrogge, K.; Jager, W.

    1984-01-01

    Some first order estimates about the production costs of seawater uranium are presented on the basis of a pilot plant with a capacity of about 100 t uranium per year. The plant is assumed to be operating at high seas using the ''adsorber loop concept'' for the contact between seawater and adsorber granulate. The effects of some process relevant components and parameters are discussed with regard to their contribution to the production costs and in order to analyse their cost-cutting potential. (orig.) [de

  20. Experimental Investigation and Modelling of a Wet Flue Gas Desulphurisation Pilot Plant

    DEFF Research Database (Denmark)

    Kiil, Søren; Michelsen, Michael Locht; Dam-Johansen, Kim

    1998-01-01

    A detailed model for a wet flue gas desulphurisation (FGD) pilot plant, based on the packed tower concept, has been developed. All important rate determining steps, absorption of SO2, oxidation of HSO3-, dissolution of limestone, and crystallisation of gypsum were included. Population balance...... equations, governing the description of particle size distributions of limestone in the plant, were derived. Model predictions were compared to experimental data such as gas phase concentration profiles of SO2, slurry pH-profiles, solids content of the slurry, liquid phase concentrations, and residual...

  1. Nuclear power plant Severe Accident Research Plan

    International Nuclear Information System (INIS)

    Larkins, J.T.; Cunningham, M.A.

    1983-01-01

    The Severe Accident Research Plan (SARP) will provide technical information necessary to support regulatory decisions in the severe accident area for existing or planned nuclear power plants, and covers research for the time period of January 1982 through January 1986. SARP will develop generic bases to determine how safe the plants are and where and how their level of safety ought to be improved. The analysis to address these issues will be performed using improved probabilistic risk assessment methodology, as benchmarked to more exact data and analysis. There are thirteen program elements in the plan and the work is phased in two parts, with the first phase being completed in early 1984, at which time an assessment will be made whether or not any major changes will be recommended to the Commission for operating plants to handle severe accidents. Additionally at this time, all of the thirteen program elements in Chapter 5 will be reviewed and assessed in terms of how much additional work is necessary and where major impacts in probabilistic risk assessment might be achieved. Confirmatory research will be carried out in phase II to provide additional assurance on the appropriateness of phase I decisions. Most of this work will be concluded by early 1986

  2. Basis for snubber aging research: Nuclear Plant Aging Research Program

    International Nuclear Information System (INIS)

    Brown, D.P.; Palmer, G.R.; Werry, E.V.; Blahnik, D.E.

    1990-01-01

    This report describes a research plan to address the safety concerns of aging in snubbers used on piping and equipment in commercial nuclear power plants. The work is to be performed under Phase 2 of the Snubber Aging Study of the Nuclear Plant Aging Research Program of the US Nuclear Regulatory Commission with the Pacific Northwest Laboratory (PNL) as the prime contractor. Research conducted by PNL under Phase 1 provided an initial assessment of snubber operating experience and was primarily based on a review of licensee event reports. The work proposed is an extension of Phase 1 and includes research at nuclear power plants and in test laboratories. Included is technical background on the design and use of snubbers in commercial nuclear power applications; the primary failure modes of both hydraulic and mechanical snubbers are discussed. The anticipated safety, technical, and regulatory benefits of the work, along with concerns of the NRC and the utilities, are also described. 21 refs., 7 figs., 1 tab

  3. Optimisation of a wet FGD pilot plant using fine limestone and organic acids

    DEFF Research Database (Denmark)

    Frandsen, Jan; Kiil, Søren; Johnsson, Jan Erik

    2001-01-01

    , but the residual limestone content in the gypsum increased to somewhere between 19 and 30 wt%, making this pH range unsuitable for use in a full-scale plant. The investigations have shown that both the addition of organic acids and the use of a limestone with a fine PSD can be used to optimise wet FGD plants. (C......The effects of adding an organic acid or using a limestone with a fine particle size distribution (PSD) have been examined in a wet flue gas desulphurisation (FGD) pilot plant. Optimisation of the plant with respect to the degree of desulphurisation and the residual limestone content of the gypsum...... has been the aim of the work. In contrast to earlier investigations with organic acids, all essential process parameters (i.e. gas phase concentration profiles of SO(2), slurry pH profiles. and residual limestone in the gypsum) were considered. Slurry concentrations of adipic acid in the range of 0...

  4. Pilot Plant for treating of spent exchange resins

    International Nuclear Information System (INIS)

    Iglesias, Alberto M.; Raffo Calderon, Maria del C.; Varani, Jose L.

    2004-01-01

    Spent exchange resins that have been accumulating during the last operational 30 years in Atucha I nuclear power plant (NPP) are a 'problematic' waste. These spent resins conform an intermediate level waste due to the total content of alpha, beta and gamma emitters (some samples of spent resins were analyzed in 2003). For this reason its treatment is more expensive since it is necessary to add more safety barriers for its final disposition and also for the radioprotection actions that are involved. Using sulfuric acid solutions it is possible to elute from the spent resins the ions that are retained. In the same operation are eluted Cobalt, Cesium and alpha emitters since that all these elements react as cations in aqueous solution. Decontamination by electrochemical methods was analyzed as an interesting method to apply after elution operation to these spent resins since that with the decontamination process it is possible to obtain a solid without activity and concentrate the activity in cells that are small in volume and its manipulation doesn't present any extra complication. Experiments made with active samples taken from the deposit were successful. Because of these results it was built a small plant to treat a batch of 100 dm 3 of wet spent exchange resins. Some problems with the material that was in the deposit together with spent resins caused that we had to plan a more complex strategy to obtain a complete decontamination of the spent resins (in this stage we used the cobalt retention cell that was described in other paper to retain Cobalt and alpha emitters and a sample of zeolites from Argentina ores to retain Cesium). Due to alpha emitters act electrochemically like cations it was possible to retain altogether with ionic Cobalt on the copper amalgam electrode. Working in the non-active lab with alcoholic solutions it was possible to retain ionic Cesium on a copper electrode (copper is covered by mercury fine film which forms a solid amalgam) with a

  5. Reacting flow simulations of supercritical water oxidation of PCB-contaminated transformer oil in a pilot plant reactor

    Directory of Open Access Journals (Sweden)

    V. Marulanda

    2011-06-01

    Full Text Available The scale-up of a supercritical water oxidation process, based on recent advancements in kinetic aspects, reactor configuration and optimal operational conditions, depends on the research and development of simulation tools, which allow the designer not only to understand the complex multiphysics phenomena that describe the system, but also to optimize the operational parameters to attain the best profit for the process and guarantee its safe operation. Accordingly, this paper reports a multiphysics simulation with the CFD software Comsol Multiphysics 3.3 of a pilot plant reactor for the supercritical water oxidation of a heavily PCB-contaminated mineral transformer oil. The proposed model was based on available information for the kinetic aspects of the complex mixture and the optimal operational conditions obtained in a lab-scale continuous supercritical water oxidation unit. The pilot plant simulation results indicate that it is not feasible to scale-up directly the optimal operational conditions obtained in the isothermal lab-scale experiments, due to the excess heat released by the exothermic oxidation reactions that result in outlet temperatures higher than 600°C, even at reactor inlet temperatures as low as 400°C. Consequently, different alternatives such as decreasing organic flowrates or a new reactor set-up with multiple oxidant injections should be considered to guarantee a safe operation.

  6. Experimental investigation of the chemical looping method on a 1 MW pilot plant; Experimentelle Untersuchung des Chemical Looping Verfahrens an einer 1 MW Versuchsanlage

    Energy Technology Data Exchange (ETDEWEB)

    Orth, Matthias

    2014-08-27

    Attempting to counteract the consequences of climate change, leading industrial nations have agreed on reducing their CO{sub 2} emissions significantly. To reach these reduction goals, it is essential to reduce the CO{sub 2} emissions in the field of energy conversion. This PHD thesis covers the field of chemical looping combustion, a technology that uses fossil fuels for energy conversion with inherent capture of CO{sub 2}. Since the research regarding chemical looping had so far focused mainly on lab scale or small scale experiments, a 1 MW pilot plant has been erected at Technische Universitaet Darmstadt in order to investigate the process in a semi-industrial scale and to check the process efficiency with commercially usable equipment. This pilot consists of two interconnected fluidized bed reactors and has an overall height of more than 11 m. In this thesis, some experiments with ilmenite - used as the oxygen carrier - are explained. Furthermore, the design, erection and commissioning of the pilot plant are presented as well as the results of the first test campaigns. The evaluation of the latter proves that the process can be handled in the design configuration and that CO{sub 2} can be safely captured in a pilot plant of this scale.

  7. Research on computer aided testing of pilot response to critical in-flight events

    Science.gov (United States)

    Giffin, W. C.; Rockwell, T. H.; Smith, P. J.

    1984-01-01

    Experiments on pilot decision making are described. The development of models of pilot decision making in critical in flight events (CIFE) are emphasized. The following tests are reported on the development of: (1) a frame system representation describing how pilots use their knowledge in a fault diagnosis task; (2) assessment of script norms, distance measures, and Markov models developed from computer aided testing (CAT) data; and (3) performance ranking of subject data. It is demonstrated that interactive computer aided testing either by touch CRT's or personal computers is a useful research and training device for measuring pilot information management in diagnosing system failures in simulated flight situations. Performance is dictated by knowledge of aircraft sybsystems, initial pilot structuring of the failure symptoms and efficient testing of plausible causal hypotheses.

  8. FY 1991 report on the results of the development of an entrained bed coal gasification power plant. Part 4. Operation of pilot plant; 1991 nendo seika hokokusho. Funryusho sekitan gaska hatsuden plant kaihatsu - Sono 4. Pilot plant unten sosa hen

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1993-01-01

    A record was summarized of the operation of the 200 t/d entrained bed coal gasification pilot plant that was constructed with the aim of establishing technology of the integrated coal gasification combined cycle power generation. As to the actual results of operation hours, the paper summarized the records of gasifier facilities, gas refining facilities, gas turbine facilities and safety environment facilities which were collected from April 1991 to January 1993. Relating to the actual results of start-up/stop, the paper summarized the records of gasifier facilities, gas refining facilities (desulfurization), gas refining facilities (dedusting), gas turbine facilities and safety environment facilities. Further, operation manuals were made for the schedule of plant start-up/stop, generalization, gasifier facilities, gas refining facilities (desulfurization), gas refining facilities (dedusting), gas turbine facilities, actual pressure/actual size combustor testing facilities and safety environment facilities. (NEDO)

  9. Research Note-Testing for Gerontological Competencies: A Pilot Study

    Science.gov (United States)

    Galambos, Colleen; Curl, Angela L.; Woodbury, Karen

    2014-01-01

    This article reports on the pilot delivery of an evaluation method to gauge student learning of gerontological competencies. Using a pretest and posttest design, data were collected on 46 students over 3 classes. Results indicated significant improvement in how students rated or perceived their competencies skill level between pretest and posttest…

  10. Field evaluation of a horizontal well recirculation system for groundwater treatment: Pilot test at the Clean Test Site Portsmouth Gaseous Diffusion Plant, Piketon, Ohio

    International Nuclear Information System (INIS)

    Muck, M.T.; Kearl, P.M.; Siegrist, R.L.

    1998-01-01

    This report presents the results of field testing a horizontal well recirculation system at the Portsmouth Gaseous Diffusion Plant (PORTS). The recirculation system uses a pair of horizontal wells, one for groundwater extraction and treatment and the other for reinjection of treated groundwater, to set up a recirculation flow field. The induced flow field from the injection well to the extraction well establishes a sweeping action for the removal and treatment of groundwater contaminants. The overall purpose of this project is to study treatment of mixed groundwater contaminants that occur in a thin water-bearing zone not easily targeted by traditional vertical wells. The project involves several research elements, including treatment-process evaluation, hydrodynamic flow and transport modeling, pilot testing at an uncontaminated site, and pilot testing at a contaminated site. The results of the pilot test at an uncontaminated site, the Clean Test Site (CTS), are presented in this report

  11. PILOT PLANT STUDY ON NATURAL WATER COAGULANTS AS COAGULAN AIDS FOR WATER SUPPLY

    Directory of Open Access Journals (Sweden)

    B BINA

    2001-06-01

    Full Text Available Introduction: Natural plant coagulants have an important role to play in provision of portable water to rural communities in the developing world. The plant material that their coagulation properties have been confirmed in previous lab scale studies and can be found widely in Iran was selected as coagulant aids. Pilot plant study was done to evaluate the efficiency of natural material such as Starch/Gum Tragacanth, Fenugreek and Yeast as coagulant aids in conjunction with comercial alum. Methods: The pilot was placed in Isfahan Water Treatment Plant (IWTP and efficiency of these materials in removal of turbidity from raw water enters the IWTP was evaluated. The results indicated while these materials were used as coagulant aids in concentration of 1-5 mg/l conjunction with alum are able to reduced the turbidity and final residuals turbidity meets the standards limits. Results: The coagulation efficiency of these material were found to be effected by certain physico-chemical factors, namely, concentration of suspended solids, divalent cation metal and time of agitation. The relative importance of these variable was evaluated. The results of COD test proved that the natural coagulant aids in the optimum doses produce no any significant organic residual. Discussion: Economical considerations showed that using of these material as coagulant aids can cause reduction in alum consumption and in some cases are more econmical than synthetic polyelectrolyte.

  12. Advanced Instrumentation, Information and Control (II&C) Research and Development Facility Buildout and Project Execution of LWRS II&C Pilot Projects 1 and 3

    Energy Technology Data Exchange (ETDEWEB)

    Ronald Farris; Johanna Oxstrand; Gregory Weatherby

    2011-09-01

    The U.S. Department of Energy (DOE) is sponsoring research, development, and deployment on light water reactor sustainability (LWRS), in which the Idaho National Laboratory (INL) is working closely with nuclear utilities to develop technologies and solutions to help ensure the safe operational life extension of current reactors. As technologies are introduced that change the operation of the plant, the LWRS pilot projects can help identify their best-advanced uses and help demonstrate the safety of these technologies. In early testing of operator performance given these emerging technologies will ensure the safety and usability of systems prior to large-scale deployment and costly verification and validation at the plant. The aim of these collaborations, demonstrations, and approaches are intended to lessen the inertia that sustains the current status quo of today's II&C systems technology, and to motivate transformational change and a shift in strategy to a long-term approach to II&C modernization that is more sustainable. Research being conducted under Pilot Project 1 regards understanding the conditions and behaviors that can be modified, either through process improvements and/or technology deployment, to improve the overall safety and efficiency of outage control at nuclear facilities. The key component of the research in this pilot project is accessing the delivery of information that will allow researchers to simulate the control room, outage control center (OCC) information, and plant status data. The simulation also allows researchers to identify areas of opportunity where plant operating status and outage activities can be analyzed to increase overall plant efficiency. For Pilot Project 3 the desire is to demonstrate the ability of technology deployment and the subsequent impact on maximizing the 'Collective Situational Awareness' of the various stakeholders in a commercial nuclear power plant. Specifically, the desire is to show positive

  13. Advanced Instrumentation, Information and Control (II and C) Research and Development Facility Buildout and Project Execution of LWRS II and C Pilot Projects 1 and 3

    International Nuclear Information System (INIS)

    Farris, Ronald; Oxstrand, Johanna; Weatherby, Gregory

    2011-01-01

    The U.S. Department of Energy (DOE) is sponsoring research, development, and deployment on light water reactor sustainability (LWRS), in which the Idaho National Laboratory (INL) is working closely with nuclear utilities to develop technologies and solutions to help ensure the safe operational life extension of current reactors. As technologies are introduced that change the operation of the plant, the LWRS pilot projects can help identify their best-advanced uses and help demonstrate the safety of these technologies. In early testing of operator performance given these emerging technologies will ensure the safety and usability of systems prior to large-scale deployment and costly verification and validation at the plant. The aim of these collaborations, demonstrations, and approaches are intended to lessen the inertia that sustains the current status quo of today's II and C systems technology, and to motivate transformational change and a shift in strategy to a long-term approach to II and C modernization that is more sustainable. Research being conducted under Pilot Project 1 regards understanding the conditions and behaviors that can be modified, either through process improvements and/or technology deployment, to improve the overall safety and efficiency of outage control at nuclear facilities. The key component of the research in this pilot project is accessing the delivery of information that will allow researchers to simulate the control room, outage control center (OCC) information, and plant status data. The simulation also allows researchers to identify areas of opportunity where plant operating status and outage activities can be analyzed to increase overall plant efficiency. For Pilot Project 3 the desire is to demonstrate the ability of technology deployment and the subsequent impact on maximizing the 'Collective Situational Awareness' of the various stakeholders in a commercial nuclear power plant. Specifically, the desire is to show positive results

  14. Laboratory and pilot plant scale study on the electrochemical oxidation of landfill leachate

    International Nuclear Information System (INIS)

    Anglada, Angela; Urtiaga, Ana M.; Ortiz, Inmaculada

    2010-01-01

    Kinetic data regarding COD oxidation were measured in a laboratory scale cell and used to scale-up an electro-oxidation process for landfill leachate treatment by means of boron-doped diamond anodes. A pilot-scale reactor with a total BDD anode area of 1.05 m 2 was designed. Different electrode gaps in the laboratory and pilot plant cells resulted in dissimilar reactor hydrodynamics. Consequently, generalised dimensionless correlations concerning mass transfer were developed in order to define the mass transfer conditions in both electrochemical systems. These correlations were then used in the design equations to validate the scale-up procedure. A series of experiments with biologically pre-treated landfill leachate were done to accomplish this goal. The evolution of ammonia and COD concentration could be well predicted.

  15. Nuclear Plant Aging Research (NPAR) program plan

    International Nuclear Information System (INIS)

    1985-07-01

    The nuclear plant aging research described in this plan is intended to resolve issues related to the aging and service wear of equipment and systems at commercial reactor facilities and their possible impact on plant safety. Emphasis has been placed on identification and characterization of the mechansims of material and component degradation during service and evaluation of methods of inspection, surveillance, condition monitoring and maintenance as means of mitigating such effects. Specifically the goals of the program are as follows: (1) to identify and characterize aging and service wear effects which, if unchecked, could cause degradation of structures, components, and systems and thereby impair plant safety; (2) to identify methods of inspection, surveillance and monitoring, or of evaluating residual life of structures, components, and systems, which will assure timely detection of significant aging effects prior to loss of safety function; and (3) to evaluate the effectiveness of storage, maintenance, repair and replacement practices in mitigating the rate and extent of degradation caused by aging and service wear

  16. Waste Isolation Pilot Plant 2003 Site Environmental Report

    Energy Technology Data Exchange (ETDEWEB)

    Washington Regulatory and Environmental Services

    2005-09-03

    The purpose of this report is to provide information needed by the DOE to assess WIPP's environmental performance and to convey that performance to stakeholders and members of the public. This report has been prepared in accordance with DOE Order 231.1A and DOE guidance. This report documents WIPP's environmental monitoring programs and their results for 2003. The WIPP Project is authorized by the DOE National Security and Military Applications of Nuclear Energy Authorization Act of 1980 (Pub. L. 96-164). After more than 20 years of scientific study and public input, WIPP received its first shipment of waste on March 26, 1999. Located in southeastern New Mexico, WIPP is the nation's first underground repository permitted to safely and permanently dispose of TRU radioactive and mixed waste (as defined in the WIPP LWA) generated through the research and production of nuclear weapons and other activities related to the national defense of the United States. TRU waste is defined in the WIPP LWA as radioactive waste containing more than 100 nanocuries (3,700 becquerels [Bq]) of alpha-emitting transuranic isotopes per gram of waste, with half-lives greater than 20 years. Exceptions are noted as high-level waste, waste that has been determined not to require the degree of isolation required by the disposal regulations, and waste the U.S. Nuclear Regulatory Commission (NRC) has approved for disposal. Most TRU waste is contaminated industrial trash, such as rags and old tools, and sludges from solidified liquids; glass; metal; and other materials from dismantled buildings. A TRU waste is eligible for disposal at WIPP if it has been generated in whole or in partby one or more of the activities listed in the Nuclear Waste Policy Act of 1982 (42 United States Code [U.S.C.] §10101, et seq.), including naval reactors development, weapons activities, verification and control technology, defense nuclear materials production, defense nuclear waste and materials by

  17. Waste Isolation Pilot Plant 2003 Site Environmental Report

    International Nuclear Information System (INIS)

    2005-01-01

    The purpose of this report is to provide information needed by the DOE to assess WIPP's environmental performance and to convey that performance to stakeholders and members of the public. This report has been prepared in accordance with DOE Order 231.1A and DOE guidance. This report documents WIPP's environmental monitoring programs and their results for 2003. The WIPP Project is authorized by the DOE National Security and Military Applications of Nuclear Energy Authorization Act of 1980 (Pub. L. 96-164). After more than 20 years of scientific study and public input, WIPP received its first shipment of waste on March 26, 1999. Located in southeastern New Mexico, WIPP is the nation's first underground repository permitted to safely and permanently dispose of TRU radioactive and mixed waste (as defined in the WIPP LWA) generated through the research and production of nuclear weapons and other activities related to the national defense of the United States. TRU waste is defined in the WIPP LWA as radioactive waste containing more than 100 nanocuries (3,700 becquerels [Bq]) of alpha-emitting transuranic isotopes per gram of waste, with half-lives greater than 20 years. Exceptions are noted as high-level waste, waste that has been determined not to require the degree of isolation required by the disposal regulations, and waste the U.S. Nuclear Regulatory Commission (NRC) has approved for disposal. Most TRU waste is contaminated industrial trash, such as rags and old tools, and sludges from solidified liquids; glass; metal; and other materials from dismantled buildings. A TRU waste is eligible for disposal at WIPP if it has been generated in whole or in partby one or more of the activities listed in the Nuclear Waste Policy Act of 1982 (42 United States Code [U.S.C.] 10101, et seq.), including naval reactors development, weapons activities, verification and control technology, defense nuclear materials production, defense nuclear waste and materials by

  18. Nuclear power plant control room task analysis. Pilot study for pressurized water reactors

    International Nuclear Information System (INIS)

    Barks, D.B.; Kozinsky, E.J.; Eckel, S.

    1982-05-01

    The purposes of this nuclear plant task analysis pilot study: to demonstrate the use of task analysis techniques on selected abnormal or emergency operation events in a nuclear power plant; to evaluate the use of simulator data obtained from an automated Performance Measurement System to supplement and validate data obtained by traditional task analysis methods; and to demonstrate sample applications of task analysis data to address questions pertinent to nuclear power plant operational safety: control room layout, staffing and training requirements, operating procedures, interpersonal communications, and job performance aids. Five data sources were investigated to provide information for a task analysis. These sources were (1) written operating procedures (event-based); (2) interviews with subject matter experts (the control room operators); (3) videotapes of the control room operators (senior reactor operators and reactor operators) while responding to each event in a simulator; (4) walk-/talk-throughs conducted by control room operators for each event; and (5) simulator data from the PMS

  19. The dispersal and impact of salt from surface storage piles the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    Reith, C.C.; Louderbough, E.T.

    1986-01-01

    A comprehensive program of ecological studies occurs at the Waste Isolation Pilot Plant (WIPP) in an effort to detect and quantify impacts of excavated salt which is stored on the surface in two piles: one having originated in 1980, the other in 1984. Both piles are surrounded by berms which channel runoff to holding ponds, so nearly all dispersal is due to the resuspension, transport, and deposition of salt particles by wind. Ecological parameters which have been monitored since 1984 include: visual evidence (via photography), soil properties, microbial activity, leaf-litter decomposition, seedling emergence, plant foliar cover, and plant species diversity. These are periodically assessed at experimental plots near the salt piles, and at control plots several kilometers away

  20. Plant lifetime management and research program

    International Nuclear Information System (INIS)

    Sakai, K.; Nagayama, M.

    1993-01-01

    The importance of nuclear power generation has been increasing in Japan. Because the lower generation cost and more stable fuel supply, in comparison with the case of fossil plants, are beneficial to Japan which has scarce natural resources. In addition, nuclear power generation is expected to help reduce carbon dioxide emission which causes global warming. In these circumstances, the safe and stable operations of nuclear power plants are of prime importance, and the frequency of unscheduled shutdown has been kept low in Japan as a result of thorough periodic inspections supported by aging management. This paper covers the development process of the aging management program and related research programs in The Kansai Electric Power Co., Inc. (KEPCO). KEPCO runs 11 nuclear power units (PWR). A Table shows the commencement date of commercial operation and operating hours for each unit. The early plants, such as Mihama-2 Unit, have been operated for more than 100,000 hours and are in the phase of aging management. Accordingly, we have been conducting aging management programs since 1987. in order to identify age-related degradation and work out countermeasures.The aging management programs have ensured safe and stable operation of nuclear power plants. Each result of the lifetime assessment has provided the information which helps establishing maintenance programs. For example, the result of the lifetime assessment has been reflected to the intervals of overhaulings and inspections, and the replacement timing of some components. In the future activities of aging management should be revised and should focus lifetime assessment on components which provoke difficulties in inspections because of high radiation exposure or high inspection cost

  1. Early-1990 status of performance assessment for the Waste Isolation Pilot Plant disposal system

    Energy Technology Data Exchange (ETDEWEB)

    Bertram-Howery, S G [Sandia National Laboratories, Albuquerque, NM (United States); Swift, P N [Tech Reps Inc., Albuquerque, NM (United States)

    1991-07-15

    This paper summarizes the early-1990 status of the performance-assessment work being done to evaluate compliance of the Waste Isolation Pilot Plant with the U.S. Environmental Protection Agency regulation 40 CFR Part 191, Subpart B. This regulation sets environmental standards for radioactive waste disposal (Environmental Radiation Protection Standards for Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Wastes). As required by Subpart B, evaluations of compliance will include probabilistic numerical simulations of repository performance and qualitative judgments. Compliance appears uncertain only in the event of human intrusion into the repository after decommissioning. Issues affecting compliance following intrusion include properties of the plugs used to seal the intruding borehole, permeability and porosity of the waste, and possible pressurization of the repository by gas generated from the organic decomposition and corrosion of the waste and containers. Research is in progress to determine the probability of intrusion and to quantify parameter uncertainties needed to include these factors in simulations of repository performance. The Department of Energy (DOE) is following two strategies to assure compliance. First, passive marker systems will be designed and implemented to reduce the likelihood of intrusion and increase the likelihood that intruders will properly reseal the repository. Second, modifications to the form of the waste and the design of the repository to achieve acceptable performance if the intruding borehole is not adequately sealed will be designed. Goals include reductions in gas generation and waste permeability and porosity. Numerous modifications are technically possible. Work in progress will evaluate proposed modifications and recommend the most promising for further testing. The DOE is confident that compliance with Subpart B of 40 CFR 191 can be established using a combination of the two strategies

  2. Key Past and Present Hydrologic Issues at the Waste Isolation Pilot Plant (WIPP)

    International Nuclear Information System (INIS)

    Lappin, Allen R.; McKenna, Sean A.; Davies, Peter B.

    2000-01-01

    In May 1998, the U.S; Environmental Protection Agency (EPA) certified the U.S. Department of Energy's (DOE) Waste Isolation Pilot Plant (WIPP) to be in compliance with applicable portions of regulations governing the permanent disposal of radioactive wastes. The step was accomplished after 24 years of effort by Sandia National Laboratories, extending from initial site selection, through extensive site characterization and under-ground experimentalization to evaluation and demonstration of regulatory compliance. The strong focus on regulatory compliance extended over approximately five years, culminating in DOE's submittal of a Compliance Certification Application (CCA) in October, 1996. Specific lessons learned from the WIPP'S transition from site characterization/experimental research to a successful regulatory compliance application may be of general interest to participants in other repository problems. In summary, the three examples considered in this paper indicate that: It is critical that site-characterization and performance-assessment (PA) activities in a repository project advance through multiple iterative interactions. This is because there are parallel paths of evolution-within a projecy On one hand, there is a natural development in the conceptual understanding of the site and repository geology, hydrology, and geochemistry over time, as well as a normal increase in the roles of regulatory/safety issues relative to technical issues. On the other hand there is ongoing evolution in numerical-modeling, experimental, and PA techniques, as well as in understanding of the insights gained from these activities. However, even if conceptual models do not change, the modeling and documentation techniques and detailed logic supporting these models will change; as additional relevant information is collected within or outside the project. Some issues related to general site-characterization or site-suitability will remain of interest, even after initial

  3. Early-1990 status of performance assessment for the Waste Isolation Pilot Plant disposal system

    International Nuclear Information System (INIS)

    Bertram-Howery, S.G.; Swift, P.N.

    1991-07-01

    This paper summarizes the early-1990 status of the performance-assessment work being done to evaluate compliance of the Waste Isolation Pilot Plant with the U.S. Environmental Protection Agency regulation 40 CFR Part 191, Subpart B. This regulation sets environmental standards for radioactive waste disposal (Environmental Radiation Protection Standards for Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Wastes). As required by Subpart B, evaluations of compliance will include probabilistic numerical simulations of repository performance and qualitative judgments. Compliance appears uncertain only in the event of human intrusion into the repository after decommissioning. Issues affecting compliance following intrusion include properties of the plugs used to seal the intruding borehole, permeability and porosity of the waste, and possible pressurization of the repository by gas generated from the organic decomposition and corrosion of the waste and containers. Research is in progress to determine the probability of intrusion and to quantify parameter uncertainties needed to include these factors in simulations of repository performance. The Department of Energy (DOE) is following two strategies to assure compliance. First, passive marker systems will be designed and implemented to reduce the likelihood of intrusion and increase the likelihood that intruders will properly reseal the repository. Second, modifications to the form of the waste and the design of the repository to achieve acceptable performance if the intruding borehole is not adequately sealed will be designed. Goals include reductions in gas generation and waste permeability and porosity. Numerous modifications are technically possible. Work in progress will evaluate proposed modifications and recommend the most promising for further testing. The DOE is confident that compliance with Subpart B of 40 CFR 191 can be established using a combination of the two strategies

  4. Continuous monitoring of natural ventilation pressure at the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    Loomis, I.M.; Wallace, K.G.

    1993-01-01

    The Waste Isolation Pilot Plant (WIPP) is a US Department of Energy research and development facility designed to demonstrate the permanent, safe disposal of US defense-generated transuranic waste. The waste storage horizon is 655 m (2150 ft) below surface in bedded salt. To date the WIPP project has not emplaced any waste. There are three intake shafts used to supply air to the underground. All air is exhausted through a single return shaft. The total design airflow during normal operations is 200 m 3 /s (424,000 cfm). The ventilation system is designed to provide separate air splits to construction, experimental, and storage activities. Separation is achieved by isolating the storage circuit from the construction or experimental circuits with bulkheads. Any air leakage must be towards the storage area of the facility. Field studies have shown that the pressure differential necessary to maintain the correct leakage direction is susceptible to the effects of natural ventilation; therefore, extensive studies and analyses have been conducted to quantify the natural ventilation effects on the WIPP underground airflow system. A component of this work is a monitoring system designed to measure the air properties necessary for calculation of the natural ventilation pressure (NVP). This monitoring system consists of measuring dry bulb temperature, relative humidity, and barometric pressure at strategic location on surface and underground. The psychometric parameters of the air are measured every fifteen minutes. From these data, trends can be determined showing the impact of NVP on the ventilation system during diurnal variations in surface climate. Both summer and winter conditions have been studied. To the author's knowledge this is the first reported instance of automatic and continuous production of time and temperature variant NVPs. This paper describes the results of the initial monitoring study

  5. Audit of selected aspects of the Waste Isolation Pilot Plant cost structure, Carlsbad, New Mexico

    International Nuclear Information System (INIS)

    1994-01-01

    The Department of Energy's (DOE) Waste Isolation Pilot Plant (WIPP), located near Carlsbad, New Mexico, is a research and development facility intended to demonstrate that transuranic waste from the Government's defense activities can be safely disposed of in a deep geologic formation. The Fiscal Year 1994 budget for WIPP is about $185 million and includes funding for the operation of WIPP and for experiments being done by other DOE facilities. DOE's current plan is for WIPP to begin receiving transuranic waste in June 1998. This audit was requested by the Assistant Secretary for Environmental Management because two recent reports, one issues by the Office of Inspector General (OIG), were critical of the staffing and cost-effectiveness of WIPP, and because of recent mission changes at WIPP. The audit team consisted of representatives from the DOE, auditors from the OIG, and technical specialists hired by the OIG to assist in the audit. The purpose of the audit was to determine whether WIPP was appropriately staffed to meet programmatic requirements in the most cost-effective manner. The Secretary of Energy expected DOE facilities to benchmark their performance against other facilities to strive for best in class status, and the Westinghouse management and operating contract for WIPP required the facility to be operated in a cost-effective manner. However, the authors determined that Westinghouse did not use benchmarks and that WIPP could be managed more cost-effectively, with fewer personnel, while maintaining its current level of excellence. They concluded that the WIPP staffing level could be significantly reduced with a decrease in costs at WIPP of about $11.4 million per year

  6. Environmental Assessment for the Above Ground Storage Capability at the Waste Isolation Pilot Plant. Draft

    Energy Technology Data Exchange (ETDEWEB)

    None

    2017-12-01

    The Waste Isolation Pilot Plant (WIPP) is the nation’s only approved repository for the disposal of defense related/defense generated transuranic (TRU) and mixed hazardous TRU waste (henceforth called TRU waste). The mission of the WIPP Project is to realize the safe disposal of TRU waste from TRU waste generator sites in the Department of Energy waste complex. The WIPP Project was authorized by Title II, Section 213(a) of Public Law 96-164 (U. S. Congress 1979). Congress designated the WIPP facility “for the express purpose of providing a research and development facility to demonstrate the safe disposal of radioactive wastes resulting from the defense activities and programs of the United States exempted from regulation by the Nuclear Regulatory Commission (NRC).” The WIPP facility is operated by the U. S. Department of Energy (DOE). Transuranic waste that is disposed in the WIPP facility is defined by Section 2(18) the WIPP Land Withdrawal Act of 1992 (LWA) (U. S. Congress, 1992) as: “waste containing more than 100 nanocuries of alpha-emitting transuranic isotopes per gram of waste, with half-lives greater than 20 years, except for: (A) high-level radioactive waste; (B) waste that the Secretary has determined, with the concurrence of the Administrator, does not need the degree of isolation required by the disposal regulations; or (C) waste that the NRC has approved for disposal on a case-by-case basis in accordance with part 61 of title 10, Code of Federal Regulations (CFR).

  7. No-migration variance petition for the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    Carnes, R.G.; Hart, J.S.; Knudtsen, K.

    1990-01-01

    The Waste Isolation Pilot Plant (WIPP) is a US Department of Energy (DOE) project to provide a research and development facility to demonstrate the safe disposal of radioactive waste resulting from US defense activities and programs. The DOE is developing the WIPP facility as a deep geologic repository in bedded salt for transuranic (TRU) waste currently stored at or generated by DOE defense installations. Approximately 60 percent of the wastes proposed to be emplaced in the WIPP are radioactive mixed wastes. Because such mixed wastes contain a hazardous chemical component, the WIPP is subject to requirements of the Resource Conservation and Recovery Act (RCRA). In 1984 Congress amended the RCRA with passage of the Hazardous and Solid Waste Amendments (HSWA), which established a stringent regulatory program to prohibit the land disposal of hazardous waste unless (1) the waste is treated to meet treatment standards or other requirements established by the Environmental Protection Agency (EPA) under section 3004(n), or (2) the EPA determines that compliance with the land disposal restrictions is not required in order to protect human health and the environment. The DOE WIPP Project Office has prepared and submitted to the EPA a no-migration variance petition for the WIPP facility. The purpose of the petition is to demonstrate, according to the requirements of RCRA section 3004(d) and 40 CFR section 268.6, that to a reasonable degree of certainty, there will be no migration of hazardous constituents from the WIPP facility for as long as the wastes remain hazardous. This paper provides an overview of the petition and describes the EPA review process, including key issues that have emerged during the review. 5 refs

  8. No-migration variance petition for the Waste Isolation Pilot Plant

    Energy Technology Data Exchange (ETDEWEB)

    Carnes, R.G.; Hart, J.S. (Benchmark Environmental Corp., Albuquerque, NM (USA)); Knudtsen, K. (International Technology Corp., Albuquerque, NM (USA))

    1990-01-01

    The Waste Isolation Pilot Plant (WIPP) is a US Department of Energy (DOE) project to provide a research and development facility to demonstrate the safe disposal of radioactive waste resulting from US defense activities and programs. The DOE is developing the WIPP facility as a deep geologic repository in bedded salt for transuranic (TRU) waste currently stored at or generated by DOE defense installations. Approximately 60 percent of the wastes proposed to be emplaced in the WIPP are radioactive mixed wastes. Because such mixed wastes contain a hazardous chemical component, the WIPP is subject to requirements of the Resource Conservation and Recovery Act (RCRA). In 1984 Congress amended the RCRA with passage of the Hazardous and Solid Waste Amendments (HSWA), which established a stringent regulatory program to prohibit the land disposal of hazardous waste unless (1) the waste is treated to meet treatment standards or other requirements established by the Environmental Protection Agency (EPA) under {section}3004(n), or (2) the EPA determines that compliance with the land disposal restrictions is not required in order to protect human health and the environment. The DOE WIPP Project Office has prepared and submitted to the EPA a no-migration variance petition for the WIPP facility. The purpose of the petition is to demonstrate, according to the requirements of RCRA {section}3004(d) and 40 CFR {section}268.6, that to a reasonable degree of certainty, there will be no migration of hazardous constituents from the WIPP facility for as long as the wastes remain hazardous. This paper provides an overview of the petition and describes the EPA review process, including key issues that have emerged during the review. 5 refs.

  9. Managing ethical issues in sexual violence research using a pilot study

    Directory of Open Access Journals (Sweden)

    S.E. Duma

    2009-09-01

    Full Text Available Conducting research in the area of sexual violence has complex ethical and practical challenges for the researcher. Managing ethical issues in sexual violence is important and can be achieved through the use of pilot studies. The primary purpose of the pilot study was to identify and manage potential ethical and practical problems that could jeopardise the main study or violate the ethical and human rights of participants in the main study on women’s journey of recovery from sexual assault. The secondary purpose was to collect preliminary data in order to determine the human, financial and time resources needed for a planned study. The methods and processes used in conducting the pilot study in the study on women’s journey of recovery are discussed according to each of the objectives of the pilot study, methods used to achieve the objective, observations or findings made during the pilot study, and implications for the main study. This article aims to demonstrate how a pilot study was used to manage identified potential ethical and practical research issues during the recruitment of participants and data collection for the research that was conducted by the first author to investigate women’s journey of recovery from sexual assault trauma within the first week following sexual assault.

  10. Waste Isolation Pilot Plant 2005 Site Environmental Report

    Energy Technology Data Exchange (ETDEWEB)

    Washington Regulatory and Environmental Services

    2006-10-13

    investigations, and defense research and development. The waste must also meet the WIPP Waste Acceptance Criteria. When TRU waste arrives at WIPP, it is transported into the Waste Handling Building. The waste containers are removed from the shipping containers, placed on the waste hoist, and lowered to the repository level of 655 m (2,150 ft; approximately 0.5 mi) below the surface. Next, the containers of waste are removed from the hoist and placed in excavated disposal rooms in the Salado Formation, a thick sequence of evaporite beds deposited approximately 250 million years ago (Figure 1.1). After each panel of seven rooms has been filled with waste, specially designed closures are emplaced. When all of WIPP's panels have been filled, at the conclusion of WIPP operations, seals will be placed in the shafts. One of the main attributes of salt, as a rock formation in which to isolate radioactive waste, is the ability of the salt to creep, that is, to deform continuously over time. Excavations into which the waste-filled drums are placed will close eventually, flowing around the drums and sealing them within the formation.

  11. Waste Isolation Pilot Plant Annual Site Environmental Report for 2005

    International Nuclear Information System (INIS)

    2006-01-01

    research and development. The waste must also meet the WIPP Waste Acceptance Criteria. When TRU waste arrives at WIPP, it is transported into the Waste Handling Building. The waste containers are removed from the shipping containers, placed on the waste hoist, and lowered to the repository level of 655 m (2,150 ft; approximately 0.5 mi) below the surface. Next, the containers of waste are removed from the hoist and placed in excavated disposal rooms in the Salado Formation, a thick sequence of evaporite beds deposited approximately 250 million years ago (Figure 1.1). After each panel of seven rooms has been filled with waste, specially designed closures are emplaced. When all of WIPP's panels have been filled, at the conclusion of WIPP operations, seals will be placed in the shafts. One of the main attributes of salt, as a rock formation in which to isolate radioactive waste, is the ability of the salt to creep, that is, to deform continuously over time. Excavations into which the waste-filled drums are placed will close eventually, flowing around the drums and sealing them within the formation.

  12. Waste water pilot plant research, development, and demonstration permit application

    International Nuclear Information System (INIS)

    1991-10-01

    Waste waters have been generated as result of operations conducted at the Hanford Facility for over 40 years. These waste waters were previously discharged to cribs, ponds, or ditches. Examples of such waste waters include steam condensates and cooling waters that have not been in contact with dangerous or mixed waste and process condensates that may have been in contact with dangerous or mixed waste. Many measures have been taken to reduce the amount of contamination being discharged in these effluents. However, some of these waste waters still require additional treatment before release to the environment. Systems are being designed and built to treat these waste waters along with any future waste waters resulting from remediation activities on the Hanford Facility

  13. Effects of foaming and antifoaming agents on the performance of a wet flue gas desulfurization pilot plant

    DEFF Research Database (Denmark)

    Qin, Siqiang; Hansen, Brian Brun; Kiil, Søren

    2014-01-01

    Foaming is a common phenomenon in industrial processes, including wet flue gas desulfurization (FGD) plants. A systemic investigation of the influence of two foaming agents, sodium dodecyl sulphate (SDS) and egg white albumin (protein), and two commercial antifoams on a wet FGD pilot plant...

  14. Experimental fact-finding in CFB biomass gasification for ECN's 500 kWth pilot-plant

    NARCIS (Netherlands)

    Kersten, Sascha R.A.; Prins, W.; van der Drift, A.; van Swaaij, Willibrordus Petrus Maria

    2003-01-01

    CFB biomass gasification has been studied by experimentation with ECN's pilot facility and a cold-flow model of this plant. Data obtained by normal operation of this plant and the results of some special experiments have provided new insight into the behavior of circulating fluidized bed reactors

  15. Pilot plant SERSE: Description and results of the experimental tests under treatment of simulated chemical liquid waste

    International Nuclear Information System (INIS)

    Calle, C.; Gili, M.; Luce, A.; Marrocchelli, A.; Pietrelli, L.; Troiani, F.

    1989-11-01

    The chemical processes for the selective separation of the actinides and long lived fission products from aged liquid wastes is described. The SERSE pilot plant is a cold facility which has been designed, by ENEA, for the engineering scale demonstration of the chemical separation processes. The experimental tests carried out in the plant are described and the results confirm the laboratory data. (author)

  16. Simulation studies of the influence of HCl absorption on the performance of a wet flue gas desulphurisation pilot plant

    DEFF Research Database (Denmark)

    Kiil, Søren; Nygaard, Helle; Johnsson, Jan Erik

    2002-01-01

    The mathematical model of Kiil et al, (Ind. Eng, Chem. Res. 37 (1998) 2792) for a wet flue gas desulphurisation (FGD) pilot plant was extended to include the simultaneous absorption of HCl. In contrast to earlier models for wet FGD plants, the inclusion of population balance equations...

  17. Design of preconcentration flow-sheet for processing Bhimunipatnam beach sands using pilot plant experiments and computer simulation

    International Nuclear Information System (INIS)

    Padmanabhan, N.P.H.; Sridhar, U.

    1993-01-01

    Simulation was carried out using a beach sand beneficiation plant simulator software, SANDBEN, currently being developed in Indian School of Mines, Dhanbad, and the results were compared and analyzed with those obtained by actual pilot plant experiments on a beach sand sample from Bhimunipatnam deposit. The software is discussed and its capabilities and limitations are highlighted. An optimal preconcentrator flow-sheet for processing Bhimunipatnam beach sand was developed by simulation and using the results of the pilot plant experiments. (author). 13 refs., 2 tabs., 3 figs

  18. Central receiver solar thermal power system, Phase 1. CRDL Item 2. Pilot plant preliminary design report. Volume III, Book 2. Collector subsystem

    Energy Technology Data Exchange (ETDEWEB)

    Hallet, Jr., R. W.; Gervais, R. L.

    1977-10-01

    The methods and plans for the manufacture of the 10-MW collector heliostats and associated controls for the pilot plant are detailed. An in-depth description of the production, installation, and verification testing of heliostats for the pilot plant is presented. Specifications for the performance, design, and test requirements for the pilot plant collector subsystem are included. Also, a heliostat location summary report is given. (WHK)

  19. Effect of ZSM-5 on the production of reformulated gasoline. Comparison between FCC pilot plant and commercial results

    International Nuclear Information System (INIS)

    Lappas, A.A.; Iatridis, D.; Vasalos, I.A.; Phyxogios, G.

    1999-01-01

    One of the more interesting ways for production of light olefins and for minimization of Gasoline olefins is the use of catalytic additives in the FCC (fluid catalytic cracking) inventory. The most widely used additive for the FCC process is the ZSM-5 which is a shape selective zeolite. When this additive is added to FCC units, it boosts the yields of LPG's olefins at the expense of gasoline, while increasing gasoline RON. The addition of ZSM-5 offers a great flexibility to a refinery since, in a relatively simple and cheap way, it can increase the RON and produces higher yields of light olefins. For all the above reasons the last years more studies are carried out in order to investigate the effect of this additive. In study presented in this paper, main emphasis was given, for the investigation of the effect of ZSM- 5 addition on FCC product distribution and especially on gasoline olefins. Moreover, in the previous literature works the ZSM-5 influences were examined using mainly fixed bed reactors. In the present study the investigation was carried out in a FCC pilot plant. The additive was also added in a commercial FCC unit of a Greek refinery (Hellenic Aspropyrgos Refinery - HAR) and thus comparison results of commercial and pilot plant test are also presented. The above study is part of a research collaboration which exists the last 10 years between the laboratory of Environmental Fuels and hydrocarbons of Chemical Process Engineering Research Institute (LEFH/CPERI) and the main Greek refineries (HEL.PETROLEUM, Motor Oil Hellas Refinery). The target of this research collaboration is i) the development of technology for the production of reformulated fuels and hydrocarbons and ii) to assist the Greek refineries to face the new regulations for environmental friendly fuels

  20. A pilot plant for removing chromium from residual water of tanneries.

    Science.gov (United States)

    Landgrave, J

    1995-02-01

    The purpose of this study is to develop a technical process for removing trivalent chromium from tannery wastewater via precipitation. This process can be considered an alternative that avoids a remediation procedure against the metal presence in industrial wastes. This process was verified in a treatment pilot plant located in León, México handling 10 m3/day of three types of effluents. The effluent streams were separated to facilitate the elimination of pollutants from each one. The process was based on in situ treatment and recycle to reduce problems associated with transportation and confinement of contaminated sludges. Two types of treatment were carried out in the pilot plant: The physical/chemical and biological treatments. Thirty-five experiments were conducted and the studied variables were the pH, type of flocculant, and its dose. The statistical significance of chromium samples was 94.7% for its precipitation and 99.7% for recovery. The objectives established for this phase of the development were accomplished and the overall efficiencies were measured for each stage in the pilot plant. The results were: a) chromium precipitation 99.5% from wastewater stream, b) chromium recovery 99% for recycling, and c) physical/chemical treatment to eliminate grease and fat at least 85% and 65 to 70% for the biological treatment. The tanning of a hide lot (350 pieces) was accomplished using 60% treated and recycled water without affecting the product quality. The recovered chromium liquor was also used in this hide tanning. This technical procedure is also applicable for removing heavy metals in other industrial sectors as well as in reducing water consumption rates, if pertinent adjustments are implemented.

  1. Development of technology for brown coal liquefaction. Design, construction and operation of pilot plant; development of 50t/d pilot plant

    Energy Technology Data Exchange (ETDEWEB)

    1986-08-01

    As for the development of 50t/d pilot plant for the development of liquefaction plant of Victorian brown coal in Austraria, outline of the contents about the second stage construction following the first stage construction up to this time is reported from the following 4 viewpoints; 1: design of process apparatuses, 2: manufacture of apparatuses, 3: fieldwork of the construction and 4: operation of the first stage facilities. On the first item the outline of detail design made by Japanese and Australian companies is described. On the second item the acceptance of purchasing goods from Japan and Australia and the condition of inspection and quality assurance to specific principal parts are described. On the third item the supplementary construction of the first stage, contents of constructions of the second stage are described. On the fourth item, preparation for operation, target, the whole circumstances and the results of maintenance, especially review of operation technique, training of operators, and occurrence and repair of troubles are described. As other relevant works, envirommental assessment, waste disposal, enviromental monitoring for exhaust gases, drainage and working enviroments, safety measure, educational training and moreover activities for local district people and the state of labor market as the support for execution of the project are described.

  2. Perspective of the Science Advisor to the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    WEART, WENDELL D.

    1999-01-01

    In 1975 Sandia National Laboratories (SNL) was asked by the predecessor to the Department of Energy to assume responsibility for the scientific programs necessary to assure the safe and satisfactory development of a geologic repository in the salt beds of southeast New Mexico. Sandia has continued in the role of Science Advisor to the Waste Isolation Pilot Plant (WIPP) to the present time. This paper will share the perspectives developed over the past 25 years as the project was brought to fruition with successful certification by the Environmental Protection Agency (EPA) on May 13, 1998 and commencement of operations on April 26, 1999

  3. WIPP conceptual design report. Addendum F. HVAC systems energy analysis for Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    1977-04-01

    This report presents the results of a technical and economic analysis of alternative methods of meeting the heating, ventilating, and air conditioning requirements of the Waste Isolation Pilot Plant (WIPP) facilities proposed to be constructed in southeastern New Mexico. This report analyzes a total of ten WIPP structures to determine the most energy and economic efficient means of providing heating, ventilating, and air conditioning services. Additional analyses were performed to determine the merits of centralized versus dispersed refrigeration and heating facilities, and of performing supplemental domestic hot water heating with solar panels

  4. Synthesis in pilot plant scale and physical properties of sulfonated polystyrene

    Directory of Open Access Journals (Sweden)

    Martins Cristiane R.

    2003-01-01

    Full Text Available The homogenous sulfonation of polystyrene was developed in a pilot plant scale producing polymers with different sulfonation degrees (18 to 22 mole % of sulfonated styrene units. The reaction yield depends chiefly on the concentration ratio of acetyl sulfate and polystyrene. The morphological and thermal properties of the sulfonated polystyrene obtained by homogeneous sulfonation were studied by means of scanning electron microscopy, differential scanning calorimetry and thermogravimetry. The glass transition temperature of sulfonated polystyrene increases in relation to pure polystyrene and DCp was evaluated in order to confirm the strong interactions among the ~SO3H groups.

  5. Pilot plant experiments for baking of anode blocks in electrically heated ovens

    Energy Technology Data Exchange (ETDEWEB)

    Grjotheim, K. (Oslo Univ. (Norway). Dept. of Chemistry); Kvande, H. (Hydro Aluminium AS, Stabekk (Norway)); Naixiang, F.; Shiheng, Z.; An, L.; Guangxia, H. (Northeast Univ. of Technology, Shenyang, LN (China). Dept. of Non-Ferrous Metallurgy)

    1990-04-01

    Pilot plant experiments were made to bake anode blocks in electrically heated baking ovens. About 70% of the baked anodes had a specific electrical resistance between 35 and 60 {Omega}xmm{sup 2}xm{sup -1}. About 25% had higher resistances, and these were returned to the baking ovens and used as heating elements in the next baking cycle. The average electrical energy consumption was 1430 kWh per tonne of anodes produced, which is about only 60% of the energy consumption in classical oil or gas-fired baking ovens. (orig.).

  6. Waste Isolation Pilot Plant: Alcove Gas Barrier trade-off study

    International Nuclear Information System (INIS)

    Lin, M.S.; Van Sambeek, L.L.

    1992-07-01

    A modified Kepner-Tregoe method was used for a trade-off study of Alcove Gas Barrier (AGB) concepts for the Waste Isolation Pilot Plant. The AGB is a gas-constraining seal to be constructed in an alcove entrance drift. In this trade-off study, evaluation criteria were first selected. Then these criteria were classified as to their importance to the task, assigning a weighting value to each aspect. Eleven conceptual design alternatives were developed based on geometrical/geological considerations, construction materials, constructibility, and other relevant factors and evaluated

  7. A pilot plant demonstration of the vitrification of radioactive solutions using microwave power

    International Nuclear Information System (INIS)

    Morrell, M.S.; Hardwick, W.H.; Murphy, V.; Wace, P.F.

    1986-01-01

    A process has been developed that exploits the characteristics of microwave heating for the vitrification of high-level radioactive liquid waste. This process, microwave vitrification, has been successfully operated at pilot plant scale in an active cell using simulated liquid waste containing several curies of radioactivity. Excellent decontamination factors have been achieved for both volatiles and nonvolatiles with an average ruthenium decontamination factor of 490 and a gross alpha emitter decontamination factor of 100,000. Almost all the radioactivity is incorporated in a glass block

  8. Condensed listing of surface boreholes at the Waste Isolation Pilot Plant Project through 31 December 1995

    International Nuclear Information System (INIS)

    Hill, L.R.; Aguilar, R.; Mercer, J.W.; Newman, G.

    1997-01-01

    This report contains a condensed listing of Waste Isolation Pilot Plant (WIPP) project surface boreholes drilled for the purpose of site selection and characterization through 31 December 1995. The US Department of Energy (DOE) sponsored the drilling activities, which were conducted primarily by Sandia National Laboratories. The listing provides physical attributes such as location (township, range, section, and state-plane coordinates), elevation, and total borehole depth, as well as the purpose for the borehole, drilling dates, and information about extracted cores. The report also presents the hole status (plugged, testing, monitoring, etc.) and includes salient findings and references. Maps with borehole locations and times-of-drilling charts are included

  9. Mill tailings disposal and environmental monitoring at the Ningyo-Toge uranium processing pilot plant

    International Nuclear Information System (INIS)

    Iwata, I.; Kitahara, Y.; Takenaka, S.; Kurokawa, Y.

    1978-01-01

    The tailings from the uranium processing pilot plant with a maximum ore processing capacity of 50 t/d are transferred to a tailings dam. The overflow from the dam is chemically treated and through settling ponds, sand filters to be discharged into a river. The concentrations of U, 226 Ra, pH, S.S., COD, Fe, Mn, Cl and F were monitored periodically and they were all below the control values. The results of monitoring on the river bed and rice paddy soil showed no signs of accumulation of U and 226 Ra in it

  10. Recent advances in AFB biomass gasification pilot plant with catalytic reactors in a downstream slip flow

    Energy Technology Data Exchange (ETDEWEB)

    Aznar, M P; Gil, J; Martin, J A; Frances, E; Olivares, A; Caballero, M A; Perez, P [Saragossa Univ. (Spain). Dept. of Chemistry and Environment; Corella, J [Madrid Univ. (Spain)

    1997-12-31

    A new 3rd generation pilot plant is being used for hot catalytic raw gas cleaning. It is based on a 15 cm. i.d. fluidized bed with biomass throughputs of 400-650 kg/h.m{sup 2}. Gasification is performed using mixtures of steam and oxygen. The produced gas is passed in a slip flow by two reactors in series containing a calcined dolomite and a commercial reforming catalyst. Tars are periodically sampled and analysed after the three reactors. Tar conversions of 99.99 % and a 300 % increase of the hydrogen content in the gas are obtained. (author) (2 refs.)

  11. No-migration variance petition for the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    Duff, M.; Carnes, R.; Hart, J.; Hansen, R.

    1991-01-01

    The US Department of Energy (DOE) is petitioning the US Environmental Protection Agency (EPA) to allow the emplacement of hazardous wastes subject to the Resource Conservation and Recovery Act (RCRA) land disposal restrictions in the Waste Isolation Pilot Plant (WIPP). The basis of the petition is that there will be no migration of hazardous constituents from the repository for as long as the wastes remain hazardous. The EPA regulations in 40 CFR Section 268.6 identify specific criteria that must be addressed in making a demonstration of no migration. EPA's approval of this petition will allow the WIPP facility to accept wastes otherwise prohibited or restricted from land disposal. 5 refs

  12. Offgas system particulate cleaning test and evaluation for the process experimental pilot plant

    International Nuclear Information System (INIS)

    Ayers, A.L. Jr.; Gale, L.G.; Stermer, D.L.

    1990-01-01

    The process experimental pilot plant (PREPP) incinerates mixed solid waste. The exhaust gas is processed through a wet offgas cleaning system. Rapid loading of the exhaust filters has been a problem and an important contributing factor is the use of quench solution containing a relatively high concentration of dissolved solids. The dissolved solids are released as a submicron particulate when the quench solution evaporates. A series of tests were performed to better identify the nature of the problem and explore solutions to the problem involving modifications to the quench process

  13. Temperature Profile Measurements in a Newly Constructed 30-Stage 5 cm Centrifugal Contactor Pilot Plant

    International Nuclear Information System (INIS)

    Garn, Troy G.; Meikrantz, Dave H.; Greenhalgh, Mitchell R.; Law, Jack D.

    2008-01-01

    An annular centrifugal contactor pilot plant incorporating 30 stages of commercial 5 cm CINC V-02 units has been built and operated at INL during the past year. The pilot plant includes an automated process control and data acquisitioning system. The primary purpose of the pilot plant is to evaluate the performance of a large number of inter-connected centrifugal contactors and obtain temperature profile measurements within a 30-stage cascade. Additional solvent extraction flowsheet testing using stable surrogates is also being considered. Preliminary hydraulic testing was conducted with all 30 contactors interconnected for continuous counter-current flow. Hydraulic performance and system operational tests were conducted successfully but with higher single-stage rotor speeds found necessary to maintain steady interstage flow at flowrates of 1 L/min and higher. Initial temperature profile measurements were also completed in this configuration studying the performance during single aqueous and two-phase counter-current flow at ambient and elevated inlet solution temperatures. Temperature profile testing of two discreet sections of the cascade required additional feed and discharge connections. Lamp oil, a commercially available alkane mixture of C14 to C18 chains, and tap water adjusted to pH 2 were the solution feeds for all the testing described in this report. Numerous temperature profiles were completed using a newly constructed 30-stage centrifugal contactor pilot plant. The automated process control and data acquisition system worked very well throughout testing. Temperature data profiles for an array of total flowrates (FT) and contactor rpm values for both single-phase and two-phase systems have been collected with selected profiles and comparisons reported. Total flowrates (FT) ranged from 0.5-1.4 L/min with rotor speeds from 3500-4000 rpm. Solution inlet temperatures ranging from ambient up to 50 C were tested. Ambient temperature testing shows that a small

  14. Waste Isolation Pilot Plant Annual Site Environmental Report for 2014. Emended

    International Nuclear Information System (INIS)

    2015-01-01

    The purpose of the Waste Isolation Pilot Plant (WIPP) Annual Site Environmental Report for 2014 (ASER) is to provide information required by U.S. Department of Energy (DOE) Order 231.1B, Environment, Safety, and Health Reporting. Specifically, the ASER presents summary environmental data to: Characterize site environmental management performance; Summarize environmental occurrences and responses reported during the calendar year (CY); Confirm compliance with environmental standards and requirements; Highlight significant environmental accomplishments, including progress toward the DOE environmental sustainability goals made through implementation of the WIPP Environmental Management System (EMS).

  15. Waste Isolation Pilot Plant Annual Site Environmental Report for 2014. Emended

    Energy Technology Data Exchange (ETDEWEB)

    none,

    2015-09-01

    The purpose of the Waste Isolation Pilot Plant (WIPP) Annual Site Environmental Report for 2014 (ASER) is to provide information required by U.S. Department of Energy (DOE) Order 231.1B, Environment, Safety, and Health Reporting. Specifically, the ASER presents summary environmental data to: Characterize site environmental management performance; Summarize environmental occurrences and responses reported during the calendar year (CY); Confirm compliance with environmental standards and requirements; Highlight significant environmental accomplishments, including progress toward the DOE environmental sustainability goals made through implementation of the WIPP Environmental Management System (EMS).

  16. DSM energy saving pilot project report. Furniture Plant Teika, Riga, Latvia

    International Nuclear Information System (INIS)

    Ananevski, V.; Kalejs, M.; Hercogs, J.; Blumbergs, U.

    1995-07-01

    The purpose of this pilot project was to carry out energy audit into the furniture plant TEIKA and energy saving measures. Another aim was to transfer the Danish know how and experience obtained through the Danish effort in Latvian industries consumers. Therefore great attention is paid to energy mapping in order to show possibilities of the Danish methodisms. This report is a part of the Joint Latvian - Danish Project Demand Side Management and Energy Saving. It is a results of collaborative efforts between a Latvian team, consisting of the specialists from Latvenergo and on the other hand a Danish team, which was represented by the Danish Power Consult company NESA. (EG)

  17. Resource conversation and recovery act draft hazardous waste facility permit: Waste Isolation Pilot Plant (WIPP)

    International Nuclear Information System (INIS)

    1993-08-01

    Volume II contains attachments for Module II and Module III. Attachments for Module II are: part A permit application; examples of acceptable documentation; Waste Isolation Pilot Plant generator/storage site waste screening and acceptance audit program; inspection schedule and monitoring schedule; inspection log forms; personnel training course outlines; hazardous waste job position training requirements; contingency plan; closure plan; and procedures for establishing background for the underground units. One attachment, facility process information, is included for Module III. Remaining attachments for this module are in Volume III

  18. Recent advances in AFB biomass gasification pilot plant with catalytic reactors in a downstream slip flow

    Energy Technology Data Exchange (ETDEWEB)

    Aznar, M.P.; Gil, J.; Martin, J.A.; Frances, E.; Olivares, A.; Caballero, M.A.; Perez, P. [Saragossa Univ. (Spain). Dept. of Chemistry and Environment; Corella, J. [Madrid Univ. (Spain)

    1996-12-31

    A new 3rd generation pilot plant is being used for hot catalytic raw gas cleaning. It is based on a 15 cm. i.d. fluidized bed with biomass throughputs of 400-650 kg/h.m{sup 2}. Gasification is performed using mixtures of steam and oxygen. The produced gas is passed in a slip flow by two reactors in series containing a calcined dolomite and a commercial reforming catalyst. Tars are periodically sampled and analysed after the three reactors. Tar conversions of 99.99 % and a 300 % increase of the hydrogen content in the gas are obtained. (author) (2 refs.)

  19. Scientific, institutional, regulatory, political, and public acceptance of the waste isolation pilot plant transuranic waste repository

    International Nuclear Information System (INIS)

    Eriksson, L.G.

    2000-01-01

    The recent successful certification and opening of a first-of-a-kind, deep geological repository for safe disposal of long-lived, transuranic radioactive waste (TRUW) at the Waste Isolation Pilot Plant (WIPP) site, New Mexico, United States of America (USA), embody both long-standing local and wide-spread, gradually achieved, scientific, institutional, regulatory, political, and public acceptance. The related historical background and development are outlined and the main contributors to the successful siting, certification, and acceptance of the WIPP TRUW repository, which may also serve as a model to success for other radioactive waste disposal programs, are described. (author)

  20. Preliminary performance assessment for the Waste Isolation Pilot Plant, December 1992

    International Nuclear Information System (INIS)

    1992-01-01

    This volume documents model parameters chosen as of July 1992 that were used by the Performance Assessment Department of Sandia National Laboratories in its 1992 preliminary performance assessment of the Waste Isolation Pilot Plant (WIPP). Ranges and distributions for about 300 modeling parameters in the current secondary data base are presented in tables for the geologic and engineered barriers, global materials (e.g., fluid properties), and agents that act upon the WIPP disposal system such as climate variability and human-intrusion boreholes. The 49 parameters sampled in the 1992 Preliminary Performance Assessment are given special emphasis with tables and graphics that provide insight and sources of data for each parameter

  1. HTGR fuel reprocessing pilot plant: results of the sequential equipment operation

    International Nuclear Information System (INIS)

    Strand, J.B.; Fields, D.E.; Kergis, C.A.

    1979-05-01

    The second sequential operation of the HTGR fuel reprocessing cold-dry head-end pilot plant equipment has been successfully completed. Twenty standard LHGTR fuel elements were crushed to a size suitable for combustion in a fluid bed burner. The graphite was combusted leaving a product of fissile and fertile fuel particles. These particles were separated in a pneumatic classifier. The fissile particles were fractured and reburned in a fluid bed to remove the inner carbon coatings. The remaining products are ready for dissolution and solvent extraction fuel recovery

  2. An overview of performance assessment for the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    Jow, Hong-Nian; Anderson, D.R.; Marietta, M.

    1997-01-01

    This paper presents an overview of the methodology used in the recent performance assessment (PA) to support the U.S. Department of Energy (DOE) Carlsbad Area Office's (CAO's) Waste Isolation Pilot Plant (WIPP) Compliance Certification Application (CCA). The results of this recently completed WIPP PA will be presented. Major release modes contributing to the total radionuclide release to the accessible environment will be discussed. Comparison of the mean complementary cumulative distribution function (CCDF) curve against the Environmental Protection Agency (EPA) radionuclide release limits will be presented

  3. Pilot plant experiments for the denitration and mercury separation from the HEWC solutions

    International Nuclear Information System (INIS)

    Humblet, L.; Hendrickx, J.P.; Geel, J. van.

    1984-06-01

    A process development for the elimination of mercury and nitrates from the HEWC (high-enriched waste concentrates) solutions has been achieved. This process is based on the reduction of mercury to metal with formaldehyde. The pilot plant which has enabled to test the developed process is described as well as the experiments. The residual mercury concentration is of 25 mg/1 but the mechanism of the reduction is not yet known. During the denitration the nitrous vapors production calls for an oversized absorption column. The control instruments and the analytical methods are also described. (AF)β

  4. Offgas system particulate cleaning test and evaluation for the Process Experimental Pilot Plant

    International Nuclear Information System (INIS)

    Ayers, A.L. Jr.; Gale, L.G.; Stermer, D.L.

    1990-01-01

    The Process Experimental Pilot Plant (PREPP) incinerates mixed solid waste. The exhaust gas is processed through a wet offgas cleaning system. Rapid loading of the exhaust filters has been a problem and an important contributing factor is the use of a quench solution containing a relatively high concentration of dissolved solids. The dissolved solids are released as a submicron particulate when the quench solution evaporates. A series of tests were performed to better identify the nature of the problem and explore solutions to the problem involving modifications to the quench process. 2 refs., 7 figs

  5. Reconsolidation of salt as applied to permanent seals for the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    Hansen, F.D.; Callahan, G.D.; Van Sembeek, L.L.

    1993-01-01

    Reconsolidated salt is a fundamental component of the permanent seals for the Waste Isolation Pilot Plant. As regulations are currently understood and seal concepts envisioned, emplaced salt is the sole long-term seal component designed to prevent the shafts from becoming preferred pathways for rating gases or liquids. Studies under way in support of the sealing function of emplaced salt include laboratory testing of crushed salt small-scale in situ tests, constitutive modeling of crushed salt, calculations of the opening responses during operation and closure, and design practicalities including emplacement techniques. This paper briefly summarizes aspects of these efforts and key areas of future work

  6. Operating boundaries of full-scale advanced water reuse treatment plants: many lessons learned from pilot plant experience.

    Science.gov (United States)

    Bele, C; Kumar, Y; Walker, T; Poussade, Y; Zavlanos, V

    2010-01-01

    Three Advanced Water Treatment Plants (AWTP) have recently been built in South East Queensland as part of the Western Corridor Recycled Water Project (WCRWP) producing Purified Recycled Water from secondary treated waste water for the purpose of indirect potable reuse. At Luggage Point, a demonstration plant was primarily operated by the design team for design verification. The investigation program was then extended so that the operating team could investigate possible process optimisation, and operation flexibility. Extending the demonstration plant investigation program enabled monitoring of the long term performance of the microfiltration and reverse osmosis membranes, which did not appear to foul even after more than a year of operation. The investigation primarily identified several ways to optimise the process. It highlighted areas of risk for treated water quality, such as total nitrogen. Ample and rapid swings of salinity from 850 to 3,000 mg/l-TDS were predicted to affect the RO process day-to-day operation and monitoring. Most of the setpoints used for monitoring under HACCP were determined during the pilot plant trials.

  7. Decontamination and decommissioning of the EBR-I complex. Topical report No. 3. NAK disposal pilot plant test

    International Nuclear Information System (INIS)

    Commander, J.C.; Lewis, L.; Hammer, R.

    1975-06-01

    Decontamination and decommissioning of the Experimental Breeder Reactor No. 1 (EBR-I) requires processing of the primary coolant, an eutectic solution of sodium and potassium (NaK), remaining in the EBR-I primary and secondary coolant systems. While developing design criteria for the NaK processing system, reasonable justification was provided for the development of a pilot test plant for field testing some of the process concepts and proposed hardware. The objective of this activity was to prove the process concept on a low-cost, small-scale test bed. The pilot test plant criteria provided a general description of the test including: the purpose, location, description of test equipment available, waste disposal requirements, and a flow diagram and conceptual equipment layout. The pilot plant test operations procedure provided a detailed step-by-step procedure for operation of the pilot plant to obtain the desired test data and operational experience. It also spelled out the safety precautions to be used by operating personnel, including the requirement for alkali metals training certification, use of protective clothing, availability of fire protection equipment, and caustic handling procedures. The pilot plant test was performed on May 16, 1974. During the test, 32.5 gallons or 240 lb of NaK was successfully converted to caustic by reaction with water in a caustic solution. (auth)

  8. Analysis of borehole inclusion stress measurement concepts proposed for use in the Waste Isolation Pilot Plant (WIPP)

    International Nuclear Information System (INIS)

    Morgan, H.S.

    1984-01-01

    The Waste Isolation Pilot Plant (WIPP) is being developed in southeastern New Mexico by the United States Department of Energy as a research and development (RandD) facility to demonstrate the safe disposal in salt of radioactive wastes resulting from defense activities. As part of the WIPP RandD program, a series of in situ tests will be performed to determine the behavior of drifts and storage rooms in the creeping salt medium. Data obtained in these tests will be used to evaluate and improve numerical models used to compute the structural response of these drifts and rooms. Stress has been proposed as one of the parameters to be measured in the tests, and borehole inclusion stressmeters have been included in the instrumentation package

  9. The development of WIPPVENT, a windows based interactive mine ventilation simulation software program at the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    McDaniel, K.H.

    1995-01-01

    An interactive mine ventilation simulation software program (WIPPVENT) was developed at the Waste Isolation Pilot Plant (WIPP). The WIPP is a US Department of Energy (DOE) research and development project located near Carlsbad, New Mexico. The facility is designed to provide a permanent, safe underground disposal of US defense generated transuranic waste in bedded salt. In addition to it's regular functions, the underground ventilation system is engineered to prevent the uncontrolled spread of radioactive materials in the unlikely event of a release. To enhance the operability system, Westinghouse Electric Corporation has developed an interactive mine ventilation simulation software program (WIPPVENT). While WIPPVENT includes most of the functions of the commercially available simulation program VNETPC (copyright 1991 Mine Ventilation Services, Inc.), the user interface has been completely rewritten as a Windows reg-sign application and screen graphics have been added. WIPPVENT is designed to interact with the WIPP ventilation monitoring systems through the site wide Central Monitoring System

  10. Environmental assessment for the reuse of TNX as a multi-purpose pilot plant campus at the Savannah River Site

    International Nuclear Information System (INIS)

    1998-07-01

    The Department of Energy (DOE) prepared this environmental assessment (EA) to analyze the potential environmental and safety impacts of DOE planning to allow asset reuse of the TNX Area at the Savannah River Site (SRS) located near Aiken, South Carolina. The proposed action would include providing for a location for the Centers of Excellence at or adjacent to SRS and entering into a cooperative agreement with a non-profit management and operations (management firm) contractor to operate and market the TNX facilities and equipment. The area (formerly TNX) would be called a Multi-Purpose Pilot Plant Campus (MPPC) and would be used: (1) as location for technology research, development, demonstration, and commercial operations; (2) to establish partnerships with industry to develop applied technologies for commercialization; and (3) serve as administrative headquarters for Centers of Excellence in the program areas of soil remediation, radioecology, groundwater contamination, and municipal solid waste minimization

  11. Computer simulation of the off gas treatment process for the KEPCO pilot vitrification plant

    International Nuclear Information System (INIS)

    Kim, Hey Suk; Maeng, Sung Jun; Lee, Myung Chan

    1999-01-01

    Vitrification technology for treatment of low and intermediate radioactive wastes can remarkably reduce waste volume to about one twentieth of the initial volume as they are collected and converted into a very stable form. Therefore, it can minimize environmental impact when the vitrified waste is disposed of. But an off gas treatment system is necessary to apply this technology because air pollutants and radioisotopes are generated like those of other conventional incinerators during thermal oxidation process at high temperature. KEPCO designed and installed a pilot scale vitrification plant to demonstrate the feasibility of the vitrification process and then to make a conceptual design for a commercial vitrification facility. The purpose of this study was to simulate the off gas treatment system(OGTS) in order optimize the operating conditions. Mass balance and temperature profile in the off gas treatment system were simulated for different combinations of combustible wastes by computer simulation code named OGTS code and removal efficiency of each process was also calculated with change of design parameters. The OGTS code saved efforts,time and capital because scale and configuration of the system could be easily changed. The simulation result of the pilot scale off gas process as well as pilot tests will be of great use in the future for a design of the commercial vitrification facility. (author)

  12. Induced mutations - a tool in plant research

    International Nuclear Information System (INIS)

    1981-01-01

    These proceedings include 34 papers and 18 brief descriptions of poster presentations in the following areas as they are affected by induced mutations: advancement of genetics, plant evolution, plant physiology, plant parasites, plant symbioses, in vitro culture, gene ecology and plant breeding. Only a relatively small number of papers are of direct nuclear interest essentially in view of the mutations being induced by ionizing radiations. The papers of nuclear interest have been entered as separate and individual items of input

  13. Evaluation of the Waste Isolation Pilot Plant classification of systems, structures and components

    International Nuclear Information System (INIS)

    1985-07-01

    A review of the classification system for systems, structures, and components at the Waste Isolation Pilot Plant (WIPP) was performed using the WIPP Safety Analysis Report (SAR) and Bechtel document D-76-D-03 as primary source documents. The regulations of the US Nuclear Regulatory Commission (NRC) covering ''Disposal of High level Radioactive Wastes in Geologic Repositories,'' 10 CFR 60, and the regulations relevant to nuclear power plant siting and construction (10 CFR 50, 51, 100) were used as standards to evaluate the WIPP design classification system, although it is recognized that the US Department of Energy (DOE) is not required to comply with these NRC regulations in the design and construction of WIPP. The DOE General Design Criteria Manual (DOE Order 6430.1) and the Safety Analysis and Review System for AL Operation document (AL 54f81.1A) were reviewed in part. This report includes a discussion of the historical basis for nuclear power plant requirements, a review of WIPP and nuclear power plant classification bases, and a comparison of the codes and standards applicable to each quality level. Observations made during the review of the WIPP SAR are noted in the text of this reoport. The conclusions reached by this review are: WIPP classification methodology is comparable to corresponding nuclear power procedures. The classification levels assigned to WIPP systems are qualitatively the same as those assigned to nuclear power plant systems

  14. Use of Pilot Plants for Developing Used Nuclear Fuel Recycling Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Phillips, Chris; Arm, Stuart [EnergySolutions LLC (United States); Banfield, Zara; Jeapes, Andrew; Taylor, Richard [National Nuclear Laboratory (United Kingdom)

    2009-06-15

    EnergySolutions and its teaming partners are working with the US Department of Energy (DOE) to develop processes, equipment and facilities for recycling used nuclear fuel (UNF). Recycling significantly reduces the volume of wastes that ultimately will be consigned to the National Geologic Repository, enables the re-use in new fuel of the valuable uranium and plutonium in the UNF, and allows the long-lived minor actinides to be treated separately so they do not become long term heat emitters in the Repository. A major requirement of any new UNF recycling facility is that pure plutonium is not separated anywhere in the process, so as to reduce the nuclear proliferation attractiveness of the facility. EnergySolutions and its team partner the UK National Nuclear Laboratory (NNL) have developed the NUEX process to achieve this and to handle appropriately the treatment of other species such as krypton, tritium, neptunium and technetium. NUEX is based on existing successful commercial UNF recycling processes deployed in the UK, France and imminently in Japan, but with a range of modifications to the flowsheet to keep some uranium with the plutonium at all times and to minimize aerial and liquid radioactive discharges. NNL's long-term experience in developing the recycling and associated facilities at the Sellafield site in the UK, and its current duties to support technically the operation of the Thermal Oxide Reprocessing Plant (THORP) at Sellafield provides essential input to the design of the US NUEX-based facility. Development work for THORP and other first-of-kind nuclear plants employed miniature scale fully radioactive through large scale inactive pilot plants. The sequence of development work that we have found most successful is to (i) perform initial process development at small (typically 1/5000) scale in gloveboxes using trace active materials, (ii) demonstrate the processes at the same small scale with actual irradiated fuel in hot cells and (iii

  15. Operation of a semi-technical pilot plant for nuclear aided steam gasification of coal

    International Nuclear Information System (INIS)

    Kirchhoff, R.; Heek, K.H. van; Juentgen, H.; Peters, W.

    1984-01-01

    After intensive investigations on a small scale, the principle of the process has been tested in a semi-technical pilot plant. In its gasifier a fluidized bed of approx. 1 m 2 cross-section and of up to 4 m height is operated at 40 bar. Heat is supplied to the bed from an immersed heat exchanger with helium flowing through it, which is heated electrically. The plant was commissioned in 1976 and has been in hot operation for approx. 23000 h, over 13000 h whereof account for coal gasification. Roughly 1600 t of coal have been put through. During recent years the processing of German caking long-flame gas coal and the marked improvement of the process by the use of catalysts have been demonstrated successfully. (orig.)

  16. Pilot studies on management of ageing of nuclear power plant components: Results of Phase 1

    International Nuclear Information System (INIS)

    1992-10-01

    To facilitate cooperation between the IAEA Member States and thus to enhance the safety and reliability of operating nuclear plants the IAEA has initiated pilot studies on the management of ageing of four representative plant components: the primary nozzle of the reactor pressure vessel, a motor operated valve, the concrete containment building and instrumentation and control cables. Phase 1 of the studies has been completed and its results are presented in this report. The report documents current understanding of ageing and methods for monitoring and mitigation of this ageing for the above components, identifies existing knowledge and technology gaps and defines follow-up work to deal with these gaps. Refs, figs and tabs

  17. Chemistry research and development. Research and development semiannual progress report, January--June 1977

    International Nuclear Information System (INIS)

    Miner, F.J.

    1977-01-01

    Results of investigations and developmental activities are reported in chemical research, component research, instrumental and statistical systems, pilot plant research, and process chemistry and instrumentation

  18. Chemistry research and development. Research and development semiannual progress report, January--June 1977

    Energy Technology Data Exchange (ETDEWEB)

    Miner, F.J.

    1977-10-21

    Results of investigations and developmental activities are reported in chemical research, component research, instrumental and statistical systems, pilot plant research, and process chemistry and instrumentation. (JRD)

  19. Development of brown coal liquefaction. Design, construction and operation of a 50 t/d pilot plant

    Energy Technology Data Exchange (ETDEWEB)

    1985-08-01

    As for the development of 50t/d pilot plant for the development of liquefaction plant of Victorian brown coal in Australia, outline of the results of the researches in 1984 is reported from the following 4 viewpoints; 1: design of process apparatuses, 2: manufacture of apparatuses, 3: field work of the construction, 4: preparation for operation of the plant. On the first item, the outline of ordering designed equipment from Japanese and Australian companies is described. On the second item the acceptance of purchasing goods from Japan and Australia and promotion of the inspection and quality assurance system. On the third item, contents of the continuous construction of the first stage are described. On the fourth item, the establishment and review of rules and regulations, training and education for operators, enviromental assessment, contents of safety and maintenance work and commissioning work by the promoting department for preparation of operation are described. Moreover support works of wide range for the promotion and adoption by necessary personnel, labour unions, the state of labour and activities for local discricts are described.

  20. Reinvestigation into Closure Predictions of Room D at the Waste Isolation Pilot Plant

    Energy Technology Data Exchange (ETDEWEB)

    Reedlunn, Benjamin [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2016-10-01

    Room D was an in-situ, isothermal, underground experiment conducted at theWaste Isolation Pilot Plant between 1984 and 1991. The room was carefully instrumented to measure the horizontal and vertical closure immediately upon excavation and for several years thereafter. Early finite element simulations of salt creep around Room D under predicted the vertical closure by 4.5×, causing investigators to explore a series of changes to the way Room D was modeled. Discrepancies between simulations and measurements were resolved through a series of adjustments to model parameters, which were openly acknowledged in published reports. Interest in Room D has been rekindled recently by the U.S./German Joint Project III and Project WEIMOS, which seek to improve the predictions of rock salt constitutive models. Joint Project participants calibrate their models solely against laboratory tests, and benchmark the models against underground experiments, such as room D. This report describes updating legacy Room D simulations to today’s computational standards by rectifying several numerical issues. Subsequently, the constitutive model used in previous modeling is recalibrated two different ways against a suite of new laboratory creep experiments on salt extracted from the repository horizon of the Waste Isolation Pilot Plant. Simulations with the new, laboratory-based, calibrations under predict Room D vertical closure by 3.1×. A list of potential improvements is discussed.

  1. Effect of heating strategy on power consumption and performance of a pilot plant anaerobic digester.

    Science.gov (United States)

    Espinosa-Solares, Teodoro; Valle-Guadarrama, Salvador; Bombardiere, John; Domaschko, Max; Easter, Michael

    2009-05-01

    The effect of heating strategy on power consumption and performance of a pilot plant anaerobic digester treating chicken litter, under thermophilic conditions, has been studied. Heating strategy was evaluated using three different spans (0.2 degrees C, 0.6 degrees C, and 1.0 degree C) for triggering the temperature control system from target temperature (56.7 degrees C). The hydraulic retention time in the pilot plant digester was in the range of 32 to 37 days, varying the total solids concentration fed from 5% to 6%. The results showed that under the experimental conditions, heating was the most energy-demanding process with 95.5% of the energy used. Increments up to 7.5% and 3.8%, respectively, on mechanical and heating power consumption, were observed as the span, for triggering the temperature control system from target temperature, was increased. Under the experimental conditions studied here, an increment of 30.6% on the global biodigester performance index was observed when a span of 1.0 degree C was compared to the one of 0.2 degrees C.

  2. Study in pilot plant of the Itataia phosphoro-uraniferous ore - CE (Brazil)

    International Nuclear Information System (INIS)

    Reis Junior, J.B.; Aquino, J.A. de; Oliveira Luz, I.L. de.

    1987-01-01

    Pilot plant data have been obtained for the physical treatment studies of the Itataia, phosphoro-uraniferous ore body located in the state of Ceara-Brazil. Due to the presence of the silic-carbonated gangue, which turns the ore complex, the pilot plant operation comprised 1200 hours. From the results obtained, it was possible to stablish a basic flowsheet for the concentration process. Such process includes a grinding step followed by a cyclone disliming (d 50 =10μm). The cyclone underflow feeds the flotation step. The conventional flotation process, which envolves the direct phosphate flotation followed by cleaning steps, was not efficient due to the presence of the carbonated gangue. In fact, the presence of silicates and carbonates in the gangue required that the flotation would be carried out in two steps. The silicated gangue is eliminated in the first flotation and a phosphate concentrate with significant amount of carbonates is obtained. This concentrate is fed to the second flotation step, termed reverse flotation, where the calcite is floated and the apatite is depressed. (Author) [pt

  3. Environmentally friendly production of charcoal from empty fruit bunches using pilot plant

    International Nuclear Information System (INIS)

    Normah Mulop; Mohd Suffian Abdul Rahim

    2000-01-01

    Empty fruit bunches (EFB) from palm oil milling process are classified as palm oil waste. The EFB can be turned into valuable product such as charcoal, which can be processed further to activated carbon in order to solve some of the disposal problems. In this project, raw EFB was converted to charcoal by means of a pilot plant. A burner generating indirect heat controls the temperature of the process. The carbonization process was carried out in the absence of air at various temperatures and durations to find the optimum carbonization parameters. The study shows that the optimum operating, temperature for carbonization of EFB is 500 o C for the duration of 11/2 hours. The average fixed carbon content of the charcoal is 61.08. The high percentage of volatile matter is prevented from escaping into the air by trapping them in a series of cyclones. The double layered cyclones using water as the cooling medium, condense more volatile matter and reduces smoke exhaust. 50.7 % of ,gaseous product is condensed and 49.2 % is emitted to the atmosphere. The result is an environmental friendly pilot plant. (author)

  4. Reinvestigation into Closure Predictions of Room D at the Waste Isolation Pilot Plant

    Energy Technology Data Exchange (ETDEWEB)

    Reedlunn, Benjamin [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2016-09-27

    Room D was an in-situ, isothermal, underground experiment conducted at the Waste Isolation Pilot Plant between 1984 and 1991. The room was carefully instrumented to measure the horizontal and vertical closure immediately upon excavation and for several years thereafter. Early finite element simulations of salt creep around Room D under-predicted the vertical closure by 4.5×, causing investigators to explore a series of changes to the way Room D was modeled. Discrepancies between simulations and measurements were resolved through a series of adjustments to model parameters, which were openly acknowledged in published reports. Interest in Room D has been rekindled recently by the U.S./German Joint Project III and Project WEIMOS, which seek to improve the predictions of rock salt constitutive models. Joint Project participants calibrate their models solely against laboratory tests, and benchmark the models against underground experiments, such as room D. This report describes updating legacy Room D simulations to today’s computational standards by rectifying several numerical issues. Subsequently, the constitutive model used in previous modeling is recalibrated two different ways against a suite of new laboratory creep experiments on salt extracted from the repository horizon of the Waste Isolation Pilot Plant. Simulations with the new, laboratory-based, calibrations under-predict Room D vertical closure by 3.1×. A list of potential improvements is discussed.

  5. Study in pilot plant of the Itataia phosphoro-uraniferous ore (CE,Brazil)

    International Nuclear Information System (INIS)

    Reis Junior, J.B.; Aquino, J.A. de; Oliveira Luz, I.L. de

    1985-01-01

    Pilot plant data have been obtained for the physical treatment studies of the Itataia, phosphoro-uraniferous ore body located in the state of Ceara-Brazil. Due to the presence of the silic-carbonated gangue, which turns the ore complex, the pilot plant operation comprised 1200 hours. From the results obtained, it was possible to establish a basic flowsheet for the concentration process. Such process includes a grinding step (-65) followed by a cyclone disliming (d50 = 10μ). The cyclone underflow feeds the flotation step. The conventional flotation process, which envolves the direct phosphate flotation followed by cleaning steps, was not efficient due to the presence of the carbonated gangue. In fact, the presence of silicates and carbonates in the gangue required that the flotation would be carried out in two steps. The silicated gangue is eliminated in the first flotation and a phosphate concentrate with significant amount of carbonates is obtained. This concentrate is fed to the second flotation step, termed reverse flotation, where the calcite is floated and the apatite is depressed. (Author) [pt

  6. A Pilot Study on the effects of Music Therapy on Frontotemporal Dementia - developing a research protocol

    DEFF Research Database (Denmark)

    Ridder, Hanne Mette Ochsner; Wigram, Tony; Ottesen, Anne Marie

    2009-01-01

    , and pharmacological treatment of the psychiatric symptoms is difficult, requiring specialist proficiency in the field. Pilot study: As there is not yet sufficient research that examines the effects of non-pharmacologic treatment with this group there is a need to develop valid and reliable research protocols....... As an example of a non-pharmacologic treatment procedure music therapy was investigated. With the focus to develop a research protocol for a future larger population study a pilot study was carried out. In two case studies a combination of data collection methods were examined with the overall goal to document...... changes in intersubjectivity. In this pilot testing there was a specific interest in selecting a relevant and manageable dementia specific instrument for measuring quality of life and relating it with other instruments. Following three instruments were tested: the Altzheimers Disease-Related Quality...

  7. Membrane bio-reactor - Research, pilot installation and measurement campaign; Membranbioreaktor (MBR) - Forschung, Pilotanlage und Messkampagne - Schlussbericht

    Energy Technology Data Exchange (ETDEWEB)

    Hersener, J -L [Ingenieurbuero Hersener, Wiesendangen (Switzerland); Meier, U [Meritec GmbH, Guntershausen (Switzerland)

    2007-07-01

    This report for the Swiss Federal Office of Energy (SFOE), takes a look at a project involving a fermenter installation in Eastern Switzerland. Research work is noted, the pilot installation is described and the results of a measurement campaign are presented and commented on. The plant is able to handle about 20,000-25,000 tonnes of slurry and organic waste. The plant is built as a membrane bio-reactor and allows the separation of the digested biomass into fractions of solid and liquid fertilisers and useful water. Furthermore, a part of the separated and digested liquid is returned to the fermenter in order to improve the digestion process. For the production of electricity a 1.1 MW generator is installed. The adaptations made during the measurement period are noted and commented on. According to the authors, the results - although difficult to interpret - show that the concept of a membrane bio-reactor can work successfully.

  8. Results from trialling aqueous NH{sub 3} based post combustion capture in a pilot plant at Munmorah power station. Desorption

    Energy Technology Data Exchange (ETDEWEB)

    Yu, Hai; Morgan, Scott; Allport, Andrew; Cottrell, Aaron; Do, Thong; McGregor, James; Wardhaugh, Leigh; Feron, Paul [CSIRO Energy Centre, Mayfield West, NSW (Australia)

    2013-07-01

    Australia's Commonwealth Scientific and Industrial Research Organization (CSIRO) and Delta Electricity have tested an aqueous ammonia based post combustion capture (PCC) process in a pilot plant at Munmorah black coal fired power station. This paper presents and discusses the experimental results obtained and primarily focuses on the desorption section. A high purity of CO{sub 2} product was obtained at the stripper gas outlet with the CO{sub 2} volumetric concentration generally between 99-100% and the remainder being water and NH{sub 3}. An increase in stripper pressure/temperature can lead to a decrease in NH{sub 3} concentration in the CO{sub 2} product. The NH{sub 3} concentration can be controlled within 200 ppm without wash at a stripper pressure of 850 kPa (the maximum pressure tested) at a stripper gas outlet temperatures of 20-25 C. The solid precipitation occurred in the stripper condenser and reflux lines. Due to the low ammonia content in the solution, CO{sub 2} content in the solution was low and generally more than 50% of regeneration energy was used to heat up the solvent under the pilot plant conditions. The lowest regeneration energy obtained from the pilot plant trials is 4-4.2 MJ/kg CO{sub 2} captured. The effect of various parameters including solvent flow-rate and stripper temperature/pressure in the solvent on the regeneration energy was investigated.

  9. Pilot-plant for NOx, SO2, HCl removal from flue-gas of municipal waste incinerator by electron beam irradiation

    International Nuclear Information System (INIS)

    Doi, Takeshi; Suda, Shoichi; Morishige, Atsushi; Tokunaga, Okihiro; Aoki, Yasushi; Sato, Shoichi; Komiya, Mikihisa; Hashimoto, Nobuo; Nakajima, Michihiro.

    1992-01-01

    A pilot-Plant for NO x , SO 2 and HCl removal from flue-gas of municipal waste incinerator by electron beam irradiation was designed and its construction at Matsudo City Waste Disposal Center was planned. The flue-gas of 1,000 Nm 3 /hr is guided from the waste incinerator flue-gas line of 30,000 Nm 3 /hr to the Pilot-Plant to be processed by spraying Ca(OH) 2 slurry (NKK-LIMAR Process) and irradiating high-energy electron beam of an accelerator. NO x , SO 2 and HCl are removed simultaneously from the flue-gas by the enhanced reaction with Ca(OH) 2 under irradiation. According to the basic research performed using a small size reactor at TRCRE of JAERI, the electron beam irradiation process was proved to be very effective for these harmful gases removal. Based on this result, the Pilot-Plant was designed for the demonstration of NO x , SO 2 and HCl removal performance using electron accelerator of maximum energy 0.95 MeV and maximum power 15 kW. The designing and planning were promoted by NKK in cooperation with JAERI and Matsudo City. (author)

  10. Final Report on Pilot Studies / Final Report on Classroom Research with STEM and TESL Assessment

    DEFF Research Database (Denmark)

    Biel, Carmen; Wake, Jo Dugstad; Hesse, Friedrich

    This Deliverable is the final report on pilot studies within the NEXT-TELL project (D6.7) and furthermore comprises the Deliverable on Classroom Research with STEM and TESL Assessment (D2.9) in order to avoid redundancies between those two Deliverables.......This Deliverable is the final report on pilot studies within the NEXT-TELL project (D6.7) and furthermore comprises the Deliverable on Classroom Research with STEM and TESL Assessment (D2.9) in order to avoid redundancies between those two Deliverables....

  11. Voluntariness of consent to HIV clinical research: A conceptual and empirical pilot study.

    Science.gov (United States)

    Mamotte, Nicole; Wassenaar, Douglas

    2017-09-01

    Obtaining voluntary informed consent for research participation is an ethical imperative, yet there appears to be little consensus regarding what constitutes a voluntary consent decision. An instrument to assess influences on participants' consent decision and perceived voluntariness was developed and piloted in two South African HIV clinical trials. The pilot study found high levels of perceived voluntariness. The feeling of having no choice but to participate was significantly associated with lower perceived voluntariness. Overall the data suggest that it is possible to obtain voluntary and valid consent for research participants in ethically complex HIV clinical trials in a developing country context.

  12. Medicinal Plant Research Group, School of Pharmacy, College of ...

    African Journals Online (AJOL)

    Medicinal Plant Research Group, School of Pharmacy, College of Health Sciences, University of Nairobi,. P.O. Box 19676-00202, ... of plant used, the dosage form and procedures for preparation and ... by thermal gravimetric methods. In finely.

  13. Fiscal 1995 achievement report. Development of entrained bed coal gasification power plant (Part 4 - Pilot plant operation); 1995 nendo seika hokokusho. Funryusho sekitan gaska hatsuden plant kaihatsu - Sono 4. Pilot plant unten sosa hen

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-03-01

    The 200 tons/day entrained bed coal gasification pilot plant constructed for establishing the technology of integrated coal gasification combined cycle was subjected to operational tests, and the fiscal 1995 results are compiled. In fiscal 1995, 1328 hours and 3 minutes (8 gasification operations) was recorded with gasification furnace facility, 899 hours and 53 minutes with the gas clean-up facility, 831 hours and 27 minutes with the gas turbine facility (11 startups for the generation of 6657 MWh), and 1958 hours and 2 minutes with the treatment furnace and 1331 hours and 10 minutes with the denitration unit of the safety/environment-related facility. The details of starts and stops were described in graphs which covered Runs D13, D14-1, D14-2, E1, D15, and A14. Operating procedures were studied and compiled for the plant start/stop schedule, general guidelines, gasification furnace facility, gas clean-up facility (dry type desulfurization facility), gas clean-up facility (dry type dedusting facility), gas turbine facility, real-pressure natural-size combustor test facility, and the safety/environment-related facility. (NEDO)

  14. FY 1992 report on the results of the development of an entrained bed coal gasification power plant. Part 4. Operation of pilot plant; 1992 nendo seika hokokusho. Funryusho sekitan gaska hatsuden plant kaihatsu - Sono 4. Pilot plant unten sosa hen

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-02-01

    A record was summarized of the operation test study in FY 1992 of the 200 t/d entrained bed coal gasification pilot plant that was constructed with the aim of establishing technology of the integrated coal gasification combined cycle power generation. The operating hour of gasifier facilities in FY 1992 was 635 hours 19 minutes, and the number of times of gasification operation was 9. The operating hour of letting gas through to gas refining facilities was 549 hours 14 minutes. The operating hour of gas turbine facilities was 310 hours 18 minutes, and the generated output was 1,366.2 MWh. The operating hour of treatment furnace of safety environment facilities was 1,401 hours 4 minutes, and that of the denitrification system was 621 hours 24 minutes. As to the actual results of the start-up/stop, the paper detailedly recorded those of RUNs 10, 11, 12, 13 and D1. Further, operation manuals were made for the schedule of plant start-up/stop, gasifier facilities, gas refining facilities (dry desulfurization facilities), gas refining facilities (dry dedusting facilities), actual pressure/actual size combustor testing facilities and safety environment facilities. (NEDO)

  15. Fiscal 1994 achievement report. Development of entrained bed coal gasification power plant (Part 4 - Pilot plant operation); 1994 nendo seika hokokusho. Funryusho sekitan gaska hatsuden plant kaihatsu - Sono 4. Pilot plant unten sosa hen

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-07-01

    The 200 tons/day entrained bed coal gasification pilot plant constructed for the establishment of the technology of integrated coal gasification combined cycle power generation was operated for testing, and the results are put together. Operating hours recorded were 1347 hours and 7 minutes for the gasification furnace facility (7 gasification operations), 752 hours and 22 minutes for the gas clean-up facilities, 425 hours and 20 minutes for the gas turbine facility (6 startups for generating 2616.1 MWh), and 1852 hours for the treatment furnace and 1304 hours and 32 minutes for the denitration system in the safety/environment-related facility. Detailed graphs were drawn for the description of starts and stops in Run D8, Run D9 (1-3), Run D10, Run D11, and in Run D12. Operating procedures were studied and then compiled for the plant start-stop schedule, general guidelines, gasification furnace facility, gas clean-up facility (dry type desulfurization facility), gas clean-up facility (dry type dedusting facility), gas turbine facility, real-pressure natural-size combustor test facility, and for the safety/environment related facility. (NEDO)

  16. Fissile material holdup monitoring in the PREPP [Process Experimental Pilot Plant] process

    International Nuclear Information System (INIS)

    Becker, G.K.; Pawelko, R.J.

    1989-01-01

    The Process Experimental Pilot Plant (PREPP) is an incineration system designed to thermally process mixed transuranic (TRU) waste and TRU contaminated low-level waste. The TRU isotopic composition is that of weapons grade plutonium (Pu) which necessitates that criticality prevention measures by incorporated into the plant design and operation. Criticality safety in the PREPP process is assured through the utilization of mass and moderation control in conjunction with favorable vessel geometries. The subject of this paper concerns the Pu mass holdup instrumentation system which is an integral part of the inprocess mass control strategy. Plant vessels and components requiring real-time mass holdup measurements were selected based on their evaluated potential for achieving physically credible Pu mass loadings and associated parameters which could lead to a criticality event. If the parameters requisite to a criticality occurrence could not physically be achieved under credible plant conditions, the particular location only required periodic portable holdup monitoring. Based on these analyses five real-time holdup monitoring locations were identified for criticality assurance purposes. An additional real-time instrument is part of the system but serves primarily in the capacity of providing operational support data. 1 fig

  17. A technical pilot plant assessment of flue gas desulfurisation in a circulating fluidised bed

    Energy Technology Data Exchange (ETDEWEB)

    Gutierrez, F.J.; Ollero, P. [Universidad de Sevilla (Spain). Dept. de Ingenieria Quimica y Ambiental; Cabanillas, A.; Otero, J. [Centro de Investigaciones Energeticas y Medioambientales, (CIEMAT), Madrid (Spain)

    2002-11-01

    Flue gas desulfurisation in a circulating fluidised bed absorber (CFBA) is quite a novel dry desulfurisation technology [6th International Conference on Circulating Fluidised Beds (1999) 601] that shows significant advantages in comparison with other dry technologies and that could also be competitive with the widely-used wet FGD technology. This experimental study analyses the performance of a flue gas treatment plant comprising a CFBA and an electrostatic precipitator (ESP). The most significant aspects considered in this study are: the effect of precollecting the fly ash, the effect of the SO{sub 2} inlet concentration, the effect of power plant load changes, the contribution of the final particulate control equipment to the overall SO{sub 2} removal efficiency and the impact of the desulfurisation unit on the ESP behaviour and its final dust emissions. In addition, the behaviour of the integrated CFBA-ESP system with respect to the main operating parameters was studied by means of a fractional factorial design of experiments. All this experimental work was carried out in a 3-MWe equivalent pilot plant that processes real gases withdrawn from the Los Barrios Power Plant. Processing a flue gas with up to 2000 ppm SO{sub 2} concentration, a sulfur removal of 95-97% with a lime utilisation of 75% was achieved. A simple regression model to evaluate the efficiency of the whole system is also proposed.(author)

  18. Accounting strategy of tritium inventory in the heavy water detritiation pilot plant from ICIT Rm. Valcea

    International Nuclear Information System (INIS)

    Bidica, N.; Stefanescu, I.; Cristescu, I.; Bornea, A.; Zamfirache, M.; Lazar, A.; Vasut, F.; Pearsica, C.; Stefan, I.; Prisecaru, I.; Sindilar, G.

    2008-01-01

    In this paper we present a methodology for determination of tritium inventory in a tritium removal facility. The method proposed is based on the developing of computing models for accountancy of the mobile tritium inventory in the separation processes, of the stored tritium and of the trapped tritium inventory in the structure of the process system components. The configuration of the detritiation process is a combination of isotope catalytic exchange between water and hydrogen (LPCE) and the cryogenic distillation of hydrogen isotopes (CD). The computing model for tritium inventory in the LPCE process and the CD process will be developed basing on mass transfer coefficients in catalytic isotope exchange reactions and in dual-phase system (liquid-vapour) of hydrogen isotopes distillation process. Accounting of tritium inventory stored in metallic hydride will be based on in-bed calorimetry. Estimation of the trapped tritium inventory can be made by subtraction of the mobile and stored tritium inventories from the global tritium inventory of the plant area. Determinations of the global tritium inventory of the plant area will be made on a regular basis by measuring any tritium quantity entering or leaving the plant area. This methodology is intended to be applied to the Heavy Water Detritiation Pilot Plant from ICIT Rm. Valcea (Romania) and to the Cernavoda Tritium Removal Facility (which will be built in the next 5-7 years). (authors)

  19. Achievement report for fiscal 1981 on Sunshine Program-assisted project. Data 4. Development of coal liquefaction technology/Development of solvent extraction liquefaction technology/Development of brown coal solvent extraction plant (Development of 50t/d pilot plant); 1981 nendo sekitan ekika gijutsu no kaihatsu seika hokokusho (Shiryo 4). Yozai chushutsu ekika gijutsu no kaihatsu (kattankei yozai chushutsu plant no kaihatsu (50ton/nichi pilot plant no kaihatsu))

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1982-03-01

    Research is conducted for the development of a liquefaction plant (50t/d pilot plant) for Australia's Victorian brown coal. In fiscal 1981, using the process concept and design data obtained through the study of elements, a detailed design of a primary hydrogenation system is drawn, part of the equipment is procured, and on-site construction work is started. The book is a collection of materials which include instrumentation-related drawings covering an instrumentation loop sketch, instrument inspection specifications (flow meter, level gage, pressure gage, thermometer, regulation meter, analyzing meter, signal receiving meter, and instrument board), general specifications for electrical instrumentation facilities, etc. (NEDO)

  20. Report on the achievements in the projects subsidized by the Sunshine Project in fiscal 1981. Data 2. Development of a coal liquefaction technology - development of a solvent extraction and liquefaction technology - 'development of a brown coal based solvent extraction plant' (Development of a 50-t/d pilot plant); 1981 nendo sekitan ekika gijutsu no kaihatsu seika hokokusho (shiryo 2). Yozai chushutsu ekika gijutsu no kaihatsu (kattankei yozai chushutsu plant no kaihatsu (50ton/nichi pilot plant no kaihatsu))

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1982-03-01

    Developmental researches were carried out on a liquefaction plant for the Victoria brown coal produced in Australia (a 50-t/d pilot plant). In fiscal 1981, detailed design was performed on the primary hydrogenation system by using the process conception and the design data obtained in the element studies. Part of the devices was procured, and the site construction was begun. The present data is a collection of drawings in relation with the machine design, such as the piping specifications, standard piping drawings, piping design procedures, piping drawings, pipe lists, and device inspection specifications. In relation with the instrumentation design, the instrumentation engineering specifications and meter lists. (NEDO)

  1. Achievement report for fiscal 1981 on Sunshine Program-assisted project. Data 4. Development of coal liquefaction technology/Development of solvent extraction liquefaction technology/Development of brown coal solvent extraction plant (Development of 50t/d pilot plant); 1981 nendo sekitan ekika gijutsu no kaihatsu seika hokokusho (Shiryo 4). Yozai chushutsu ekika gijutsu no kaihatsu (kattankei yozai chushutsu plant no kaihatsu (50ton/nichi pilot plant no kaihatsu))

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1982-03-01

    Research is conducted for the development of a liquefaction plant (50t/d pilot plant) for Australia's Victorian brown coal. In fiscal 1981, using the process concept and design data obtained through the study of elements, a detailed design of a primary hydrogenation system is drawn, part of the equipment is procured, and on-site construction work is started. The book is a collection of materials which include instrumentation-related drawings covering an instrumentation loop sketch, instrument inspection specifications (flow meter, level gage, pressure gage, thermometer, regulation meter, analyzing meter, signal receiving meter, and instrument board), general specifications for electrical instrumentation facilities, etc. (NEDO)

  2. Feasibility and Pilot Studies in Palliative Care Research: A Systematic Review.

    Science.gov (United States)

    Jones, Terry A; Olds, Timothy S; Currow, David C; Williams, Marie T

    2017-07-01

    Feasibility and pilot study designs are common in palliative care research. Finding standard guidelines on the structure and reporting of these study types is difficult. In feasibility and pilot studies in palliative care research, to determine 1) how commonly a priori feasibility are criteria reported and whether results are subsequently reported against these criteria? and 2) how commonly are participants' views on acceptability of burden of the study protocol assessed? Four databases (OVID Medline, EMBASE, CINAHL, and PubMed via caresearch.com.au.) were searched. Search terms included palliative care, terminal care, advance care planning, hospice, pilot, feasibility, with a publication date between January 1, 2012 and December 31, 2013. Articles were selected and appraised by two independent reviewers. Fifty-six feasibility and/or pilot studies were included in this review. Only three studies had clear a priori criteria to measure success. Sixteen studies reported participant acceptability or burden with measures. Forty-eight studies concluded feasibility. The terms "feasibility" and "pilot" are used synonymously in palliative care research when describing studies that test for feasibility. Few studies in palliative care research outline clear criteria for success. The assessment of participant acceptability and burden is uncommon. A gold standard for feasibility study design in palliative care research that includes both clear criteria for success and testing of the study protocol for participant acceptability and burden is needed. Such a standard would assist with consistency in the design, conduct and reporting of feasibility and pilot studies. Copyright © 2017 American Academy of Hospice and Palliative Medicine. Published by Elsevier Inc. All rights reserved.

  3. Development of Pflotran Code for Waste Isolation Pilot Plant Performance Assessment

    Science.gov (United States)

    Zeitler, T.; Day, B. A.; Frederick, J.; Hammond, G. E.; Kim, S.; Sarathi, R.; Stein, E.

    2017-12-01

    The Waste Isolation Pilot Plant (WIPP) has been developed by the U.S. Department of Energy (DOE) for the geologic (deep underground) disposal of transuranic (TRU) waste. Containment of TRU waste at the WIPP is regulated by the U.S. Environmental Protection Agency (EPA). The DOE demonstrates compliance with the containment requirements by means of performance assessment (PA) calculations. WIPP PA calculations estimate the probability and consequence of potential radionuclide releases from the repository to the accessible environment for a regulatory period of 10,000 years after facility closure. The long-term performance of the repository is assessed using a suite of sophisticated computational codes. There is a current effort to enhance WIPP PA capabilities through the further development of the PFLOTRAN software, a state-of-the-art massively parallel subsurface flow and reactive transport code. Benchmark testing of the individual WIPP-specific process models implemented in PFLOTRAN (e.g., gas generation, chemistry, creep closure, actinide transport, and waste form) has been performed, including results comparisons for PFLOTRAN and existing WIPP PA codes. Additionally, enhancements to the subsurface hydrologic flow mode have been made. Repository-scale testing has also been performed for the modified PFLTORAN code and detailed results will be presented. Ultimately, improvements to the current computational environment will result in greater detail and flexibility in the repository model due to a move from a two-dimensional calculation grid to a three-dimensional representation. The result of the effort will be a state-of-the-art subsurface flow and transport capability that will serve WIPP PA into the future for use in compliance recertification applications (CRAs) submitted to the EPA. Sandia National Laboratories is a multi-mission laboratory managed and operated by National Technology and Engineering Solutions of Sandia, LLC., a wholly owned subsidiary of

  4. Use of Performance Assessment in Support of Waste Isolation Pilot Plant (WIPP) Programmatic Activity Planning

    International Nuclear Information System (INIS)

    BASABILVAZO, GEORGE; JOW, HONG-NIAN; LARSON, KURT W.; MARIETTA, MELVIN G.

    1999-01-01

    The Waste Isolation Pilot Plant (WIPP) is being developed by the U.S. Department of Energy (DOE) for the geologic (deep underground) disposal of transuranic (TRU) waste. A Compliance Certification Application (CCA) of the WIPP for such disposal was submitted to the U.S. Environmental Protection Agency (EPA) in October 1996, and was approved by EPA in May 1998. In June 1998, two separate, but related, lawsuits were filed, one against DOE and one against EPA. On March 22, 1999, the court ruled in favor of DOE, and on March 26, 1999, DOE formally began disposal operations at the WIPP for non-mixed (non-hazardous) TRU waste. Before the WIPP can begin receiving mixed (hazardous) TRU waste, a permit from the State of New Mexico for hazardous waste disposal needs to be issued. It is anticipated that the State of New Mexico will issue a hazardous waste permit by November 1999. It is further anticipated that the EPA lawsuit will be resolved by July 1999. Congress (Public Law 102-579, Section 8(f)) requires the WIPP project to be recertified by the EPA at least as frequently as once every five years from the first receipt of TRU waste at the WIPP site. As part of the DOE's WIPP project recertification strategy, Sandia National Laboratories (SNL) has used systems analysis and performance assessment to prioritize its scientific and engineering research activities. Two 1998 analyses, the near-field systems analysis and the annual sensitivity analysis, are discussed here. Independently, the two analyses arrived at similar conclusions regarding important scientific activities associated with the WIPP. The use of these techniques for the recent funding allocations at SNL's WIPP project had several beneficial effects. It increased the level of acceptance among project scientists that management had fairly and credibly compared alternatives when making prioritization decisions. It improved the ability of SNL and its project sponsor, the Carlsbad Area Office of the DOE, to

  5. Plant biology research and training for the 21st century

    Energy Technology Data Exchange (ETDEWEB)

    Kelly, K. [ed.

    1992-12-31

    The committee was assembled in response to a request from the National Science Foundation (NSF), the US Department of Agriculture (USDA), and the US Department of Energy (DoE). The leadership of these agencies asked the National Academy of Sciences through the National Research Council (NRC) to assess the status of plant-science research in the United States in light of the opportunities arising from advances inother areas of biology. NRC was asked to suggest ways of accelerating the application of these new biologic concepts and tools to research in plant science with the aim of enhancing the acquisition of new knowledge about plants. The charge to the committee was to examine the following: Organizations, departments, and institutions conducting plant biology research; human resources involved in plant biology research; graduate training programs in plant biology; federal, state, and private sources of support for plant-biology research; the role of industry in conducting and supporting plant-biology research; the international status of US plant-biology research; and the relationship of plant biology to leading-edge research in biology.

  6. Plant biology research and training for the 21st century

    Energy Technology Data Exchange (ETDEWEB)

    Kelly, K. (ed.)

    1992-01-01

    The committee was assembled in response to a request from the National Science Foundation (NSF), the US Department of Agriculture (USDA), and the US Department of Energy (DoE). The leadership of these agencies asked the National Academy of Sciences through the National Research Council (NRC) to assess the status of plant-science research in the United States in light of the opportunities arising from advances inother areas of biology. NRC was asked to suggest ways of accelerating the application of these new biologic concepts and tools to research in plant science with the aim of enhancing the acquisition of new knowledge about plants. The charge to the committee was to examine the following: Organizations, departments, and institutions conducting plant biology research; human resources involved in plant biology research; graduate training programs in plant biology; federal, state, and private sources of support for plant-biology research; the role of industry in conducting and supporting plant-biology research; the international status of US plant-biology research; and the relationship of plant biology to leading-edge research in biology.

  7. Effect of different plant species in pilot constructed wetlands for wastewater reuse in agriculture

    Directory of Open Access Journals (Sweden)

    Salvatore Barbagallo

    2013-09-01

    Full Text Available In this paper the first results of an experiment carried out in Southern Italy (Sicily on the evapotranspiration (ET and removal in constructed wetlands with five plant species are presented. The pilot plant used for this study is made of twelve horizontal sub-surface flow constructed wetlands (each with a surface area of 4.5 m2 functioning in parallel, and it is used for tertiary treatment of part of the effluents from a conventional municipal wastewater treatment plant (trickling filter. Two beds are unplanted (control while ten beds are planted with five different macrophyte species: Cyperus papyrus, Vetiveria zizanoides, Miscanthus x giganteus, Arundo donax and Phragmites australis (i.e., every specie is planted in two beds to have a replication. The influent flow rate is measured in continuous by an electronic flow meter. The effluent is evaluated by an automatic system that measure the discharged volume for each bed. Physical, chemical and microbiological analyses were carried out on wastewater samples collected at the inlet of CW plant and at the outlet of the twelve beds. An automatic weather station is installed close to the experimental plant, measuring air temperature, wind speed and direction, rainfall, global radiation, relative humidity. This allows to calculate the reference Evapotranspiration (ET0 with the Penman-Monteith formula, while the ET of different plant species is measured through the water balance of the beds. The first results show no great differences in the mean removal performances of the different plant species for TSS, COD and E.coli, ranged from, respectively, 82% to 88%, 60% to 64% and 2.7 to 3.1 Ulog. The average removal efficiency of nutrient (64% for TN; 61 for NH4-N, 31% for PO4-P in the P.australis beds was higher than that other beds. From April to November 2012 ET measured for plant species were completely different from ET0 and ETcontrol, underlining the strong effect of vegetation. The cumulative

  8. Experiment research on cognition reliability model of nuclear power plant

    International Nuclear Information System (INIS)

    Zhao Bingquan; Fang Xiang

    1999-01-01

    The objective of the paper is to improve the reliability of operation on real nuclear power plant of operators through the simulation research to the cognition reliability of nuclear power plant operators. The research method of the paper is to make use of simulator of nuclear power plant as research platform, to take present international research model of reliability of human cognition based on three-parameter Weibull distribution for reference, to develop and get the research model of Chinese nuclear power plant operators based on two-parameter Weibull distribution. By making use of two-parameter Weibull distribution research model of cognition reliability, the experiments about the cognition reliability of nuclear power plant operators have been done. Compared with the results of other countries such USA and Hungary, the same results can be obtained, which can do good to the safety operation of nuclear power plant

  9. 2011 Plant Lipids: Structure, Metabolism, & Function Gordon Research Conference

    Energy Technology Data Exchange (ETDEWEB)

    Christopher Benning

    2011-02-04

    This is the second Gordon Research Conference on 'Plant Lipids: Structure, Metabolism & Function'. It covers current topics in lipid structure, metabolism and function in eukaryotic photosynthetic organisms including seed plants, algae, mosses and ferns. Work in photosynthetic bacteria is considered as well as it serves the understanding of specific aspects of lipid metabolism in plants. Breakthroughs are discussed in research on plant lipids as diverse as glycerolipids, sphingolipids, lipids of the cell surface, isoprenoids, fatty acids and their derivatives. The program covers nine concepts at the forefront of research under which afore mentioned plant lipid classes are discussed. The goal is to integrate areas such as lipid signaling, basic lipid metabolism, membrane function, lipid analysis, and lipid engineering to achieve a high level of stimulating interaction among diverse researchers with interests in plant lipids. One Emphasis is on the dynamics and regulation of lipid metabolism during plant cell development and in response to environmental factors.

  10. Pilot plant development of a new catalytic process for improved electrostatic separation of fly-ash in coal fired power plants

    Energy Technology Data Exchange (ETDEWEB)

    Olivares del Valle, J.; Salvador Martinez, L.; Muniz Baum, B.; Cortes Galeano, V. [University of Seville, Seville (Spain). Chemical and Environmental Engineering Dept.

    1996-12-31

    A new catalytic process for flue gas conditioning in pulverized coal fired power plants is outlined. Vanadium and platinum catalysts specifically prepared on ceramic honeycomb monoliths to oxidize SO{sub 2} into SO{sub 3} have been tested and evaluated at pilot scale. 10 refs., 3 figs., 2 tabs.

  11. Evaluation and use of remotely piloted aircraft systems for operations and research - RxCADRE 2012

    Science.gov (United States)

    Thomas J. Zajkowski; Matthew B. Dickinson; J. Kevin Hiers; William Holley; Brett W. Williams; Alexander Paxton; Otto Martinez; Gregory W. Walker

    2016-01-01

    Small remotely piloted aircraft systems (RPAS), also known as unmanned aircraft systems (UAS), are expected to provide important contributions to wildland fire operations and research, but their evaluation and use have been limited. Our objectives were to leverage US Air Force-controlled airspace to (1) deploy RPAS in support of the 2012 Prescribed Fire...

  12. Evaluation of the Pilot Mentoring Program at the Research Foundation for SUNY

    Science.gov (United States)

    Henderson-Harr, Amy; Caggiano-Siino, Kathleen; Prewitt, Ashlee

    2016-01-01

    This article provides a description of an 18-month pilot program focused on the leadership development of the next generation of research administrators (RAs) in the State University of New York system (SUNY). The key questions for the evaluators were: 1) can we create a developmental program that effectively prepares the next generation of RAs;…

  13. Integrating Research-Informed Teaching within an Undergraduate Level 4 (Year 1) Diagnostic Radiography Curriculum: A Pilot Study

    Science.gov (United States)

    Higgins, Robert; Hogg, Peter; Robinson, Leslie

    2013-01-01

    This article discusses the piloting and evaluation of the Research-informed Teaching experience (RiTe) project. The aim of RiTe was to link teaching and learning with research within an undergraduate diagnostic radiography curriculum. A preliminary pilot study of RiTe was undertaken with a group of level 4 (year 1) volunteer BSc (Hons) diagnostic…

  14. Operation of a pilot plant for the maize desinfestation by irradiation

    International Nuclear Information System (INIS)

    Piedad Beneitez, A. de la.

    1975-01-01

    The paper describes the components and the operation of a pilot plant for radiation disinfestation of maize that has been set up at the Van de Graaff Accelerator Laboratory of the Physics Institute (Mexican National Autonomous University). The Laboratory is operated jointly by the Physics Institute and Technology Programme (National Nuclear Energy Institute). A section is included on the fundamentals and terminology relating to the applications of radiation. The present status of radiation disinfestation of maize in other countries is described, together with what has been achieved at this Laboratory. Another section deals in detail with the main components of the plant and its operation. Finally, the authors describe the experiments carried out with the plant to establish optimum conditions of operation prior to the irradiation of maize on a major scale. One such experiment involved determining the uniformity of the beam over the irradiation zone, for which purpose polyvinyl chloride films were used as dosimeters. The dose received by the maize in a single run past the irradiation head was likewise determined from the thermoluminescent response of powdered lithium fluoride irradiated in capsules along with the maize kernels. (author)

  15. A realistic approach to modeling an in-duct desulfurization process based on an experimental pilot plant study

    Energy Technology Data Exchange (ETDEWEB)

    Ortiz, F.J.G.; Ollero, P. [University of Seville, Seville (Spain)

    2008-07-15

    This paper has been written to provide a realistic approach to modeling an in-duct desulfurization process and because of the disagreement between the results predicted by published kinetic models of the reaction between hydrated lime and SO{sub 2} at low temperature and the experimental results obtained in pilot plants where this process takes place. Results were obtained from an experimental program carried out in a 3-MWe pilot plant. Additionally, five kinetic models, from the literature, of the reaction of sulfation of Ca(OH){sub 2} at low temperatures were assessed by simulation and indicate that the desulfurization efficiencies predicted by them are clearly lower than those experimentally obtained in our own pilot plant as well as others. Next, a general model was fitted by minimizing the difference between the calculated and the experimental results from the pilot plant, using Matlab{sup TM}. The parameters were reduced as much as possible, to only two. Finally, after implementing this model in a simulation tool of the in-duct sorbent injection process, it was validated and it was shown to yield a realistic approach useful for both analyzing results and aiding in the design of an in-duct desulfurization process.

  16. Determination of Waste Isolation Pilot Plant (WIPP) management and institutional requirements documents for contact-handled (CH) critical systems

    International Nuclear Information System (INIS)

    1990-01-01

    This document lists the critical requirements documents applicable to the receipt of contact-handled waste at the Waste Isolation Pilot Plant. It also describes the processes used to determine the applicability of each document. This analysis is based on the applicable documents that were in effect in the February 1988 time frame. 2 refs

  17. Hanford site as it relates to an alternative site for the Waste Isolation Pilot Plant: an environmental description

    Energy Technology Data Exchange (ETDEWEB)

    Fecht, K.R. (ed.)

    1978-12-01

    The use of basalt at Hanford as an alternative for the Waste Isolation Pilot Plant (WIPP) would require that the present Basalt Waste Isolation Program (BWIP) at Hanford be expanded to incorporate the planned WIPP functions, namely the permanent storage of transuranic (TRU) wastes. This report discusses: program costs, demography, ecology, climatology, physiography, hydrology, geology, seismology, and historical and archeological sites. (DLC)

  18. Existing conditions socioeconomic portion. Waste isolation pilot plant environmental impact report, chapter 2, sections 2. 2, 2. 3

    Energy Technology Data Exchange (ETDEWEB)

    1978-07-01

    The population characteristics and the economic setting of Eddy and Lea Counties, New Mexico, are reviewed as related to site selection for a radioactive waste isolation pilot plant. Sections are included on population distribution, basic industries, trade and services, financial resources, personal income, tourism, labor force, employment, land use, water systems, utilities, transportation, and local government. (JRD)

  19. Hanford site as it relates to an alternative site for the Waste Isolation Pilot Plant: an environmental description

    International Nuclear Information System (INIS)

    Fecht, K.R.

    1978-12-01

    The use of basalt at Hanford as an alternative for the Waste Isolation Pilot Plant (WIPP) would require that the present Basalt Waste Isolation Program (BWIP) at Hanford be expanded to incorporate the planned WIPP functions, namely the permanent storage of transuranic (TRU) wastes. This report discusses: program costs, demography, ecology, climatology, physiography, hydrology, geology, seismology, and historical and archeological sites

  20. Resource Conservation and Recovery Act, Part B permit application [for the Waste Isolation Pilot Plant (WIPP)]. Volume 1, Revision 3

    Energy Technology Data Exchange (ETDEWEB)

    1993-03-01

    This volume includes the following chapters: Waste Isolation Pilot Plant RCRA A permit application; facility description; waste analysis plan; groundwater monitoring; procedures to prevent hazards; RCRA contingency plan; personnel training; corrective action for solid waste management units; and other Federal laws.

  1. Establishment of a pilot plant for pesticide formulation, union of myanmar. Technical report: Findings and recommendations (May 1992)

    Energy Technology Data Exchange (ETDEWEB)

    Bendefy, I

    1992-05-08

    The expert report on establishment of a pilot plant for pesticides formulation in Myanmar covers: (1) project background; (2) laboratory, quality control; (3) use of domestic raw materials kerosene; (4) energy supply (diesel engines); (5) bottling and packaging; (6) transport and telecommunications; (7) industrial safety; and (8) management.

  2. Existing conditions socioeconomic portion. Waste isolation pilot plant environmental impact report, chapter 2, sections 2.2, 2.3

    International Nuclear Information System (INIS)

    1978-07-01

    The population characteristics and the economic setting of Eddy and Lea Counties, New Mexico, are reviewed as related to site selection for a radioactive waste isolation pilot plant. Sections are included on population distribution, basic industries, trade and services, financial resources, personal income, tourism, labor force, employment, land use, water systems, utilities, transportation, and local government

  3. 10-MWe solar-thermal central-receiver pilot plant: collector subsystem foundation construction. Revision No. 1

    Energy Technology Data Exchange (ETDEWEB)

    1979-12-18

    Bid documents are provided for the construction of the collector subsystem foundation of the Barstow Solar Pilot Plant, including invitation to bid, bid form, representations and certifications, construction contract, and labor standards provisions of the Davis-Bacon Act. Instructions to bidders, general provisions and general conditions are included. Technical specifications are provided for the construction. (LEW)

  4. Pilot plant for the radioactive decontamination of spent oils; Planta piloto para la descontaminacion radiactiva de aceites gastados

    Energy Technology Data Exchange (ETDEWEB)

    Flores E, R.M.; Ortiz O, H.V.; Cisneros L, L.; Lopez G, R. [Instituto Nacional de Investigaciones Nucleares, A.P. 18-1027, 11801 Mexico D.F. (Mexico)

    2002-07-01

    In this work the operation parameters obtained in the laboratory of oil storage are presented, as well as the operations which shape the pilot plant, the design criteria and the basic design of the core equipment of the developed process. Finally, the comparative results obtained the decontamination process of oil are given as well as laboratory scale. (Author)

  5. Demonstration of a 100-kWth high-temperature solar thermochemical reactor pilot plant for ZnO dissociation

    Science.gov (United States)

    Koepf, E.; Villasmil, W.; Meier, A.

    2016-05-01

    Solar thermochemical H2O and CO2 splitting is a viable pathway towards sustainable and large-scale production of synthetic fuels. A reactor pilot plant for the solar-driven thermal dissociation of ZnO into metallic Zn has been successfully developed at the Paul Scherrer Institute (PSI). Promising experimental results from the 100-kWth ZnO pilot plant were obtained in 2014 during two prolonged experimental campaigns in a high flux solar simulator at PSI and a 1-MW solar furnace in Odeillo, France. Between March and June the pilot plant was mounted in the solar simulator and in-situ flow-visualization experiments were conducted in order to prevent particle-laden fluid flows near the window from attenuating transparency by blocking incoming radiation. Window flow patterns were successfully characterized, and it was demonstrated that particle transport could be controlled and suppressed completely. These results enabled the successful operation of the reactor between August and October when on-sun experiments were conducted in the solar furnace in order to demonstrate the pilot plant technology and characterize its performance. The reactor was operated for over 97 hours at temperatures as high as 2064 K; over 28 kg of ZnO was dissociated at reaction rates as high as 28 g/min.

  6. The Purlex process - a description of the pilot plant leading to the use of the process in South Africa

    International Nuclear Information System (INIS)

    Tunley, T.H.; Faure, A.

    1969-01-01

    This report briefly describes the pilot plant and highlights the important findings of the testwork. Particular attention is paid to the problems which arose during the two-year period of operation and the steps taken to solve these problems. Average values are given for the important parameters for the various test periods

  7. Technical basis for external dosimetry at the Waste Isolation Pilot Plant (WIPP)

    International Nuclear Information System (INIS)

    Bradley, E.W.; Wu, C.F.; Goff, T.E.

    1993-01-01

    The WIPP External Dosimetry Program, administered by Westinghouse Electric Corporation, Waste Isolation Division, for the US Department of Energy (DOE), provides external dosimetry support services for operations at the Waste Isolation Pilot Plant (WIPP) Site. These operations include the receipt, experimentation with, storage, and disposal of transuranic (TRU) wastes. This document describes the technical basis for the WIPP External Radiation Dosimetry Program. The purposes of this document are to: (1) provide assurance that the WIPP External Radiation Dosimetry Program is in compliance with all regulatory requirements, (2) provide assurance that the WIPP External Radiation Dosimetry Program is derived from a sound technical base, (3) serve as a technical reference for radiation protection personnel, and (4) aid in identifying and planning for future needs. The external radiation exposure fields are those that are documented in the WIPP Final Safety Analysis Report

  8. A formal expert judgment procedure for performance assessments of the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    Trauth, K.M.; Guzowski, R.V.; Hora, S.C.

    1994-09-01

    The Waste Isolation Pilot Plant (WIPP) is an experimental facility located in southeastern New Mexico. It has been designed to determine the feasibility of the geologic disposal of defense-generated transuranic waste in a deep bedded-salt formation. The WIPP was also designed for disposal and will operate in that capacity if approved. The WIPP Performance Assessment Department at Sandia National Laboratories has been conducting analyses to assess the long-term performance of the WIPP. These analyses sometimes require the use of expert judgment. This Department has convened several expert-judgment panels and from that experience has developed an internal quality-assurance procedure to guide the formal elicitation of expert judgment. This protocol is based on the principles found in the decision-analysis literature

  9. Environmental management assessment of the Waste Isolation Pilot Plant (WIPP), Carlsbad, New Mexico

    International Nuclear Information System (INIS)

    1993-07-01

    This document contains the results of the Environmental Management Assessment of the Waste Isolation Pilot Plant (WIPP). This Assessment was conducted by EH-24 from July 19 through July 30, 1993 to advise the Secretary of Energy of the adequacy of management systems established at WIPP to ensure the protection of the environment and compliance with Federal, state, and DOE environmental requirements. The mission of WIPP is to demonstrate the safe disposal of transuranic (TRU) waste. During this assessment, activities and records were reviewed and interviews were conducted with personnel from the management and operating contractors. This assessment revealed that WIPP's environmental safety and health programs are satisfactory, and that all levels of the Waste Isolation Division (WID) management and staff consistently exhibit a high level of commitment to achieve environmental excellence

  10. Design analysis of engineered alternatives for the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    Myers, J.; Djordjevic, S.; Adams, M.; Spangler, L.; Valdez, J.; Vetter, D.; Drez, P.

    1991-01-01

    The effectiveness of several engineered alternatives, designed to enhance the performance of the Waste Isolation Pilot Plant (WIPP), were evaluated relative to the performance of the baseline design. This evaluation was performed using a computer program referred to as the Design Analysis Model which couples salt creep closure, brine inflow, gas generation and dissipation to realistically simulate these interrelated processes over a 10,000 year period following the decommissioning of the repository. Analyses of the baseline design and nine alternative designs were performed for the undisturbed repository conditions, as well as three human intrusion events. Improvements in repository performance of up to four orders of magnitude were predicted for various engineered alternative waste forms. 6 refs., 8 figs., 1 tab

  11. Scenario development for the Waste Isolation Pilot Plant: Building confidence in the assessment

    International Nuclear Information System (INIS)

    Galson, D.A.; Swift, P.N.

    1994-01-01

    Scenario developments is part of the iterative performance assessment (PA) process for the Waste Isolation Pilot Plant (WIPP). Scenario development for the WIPP has been the subject of intense external review, and is certain to be the subject of continued scrutiny as the project proceeds toward regulatory compliance. The principal means of increasing confidence is this aspect of the PA will be through the use of a systematic and thorough procedure toward developing the scenarios and conceptual models on which the assessment is to be based. Early and ongoing interaction with project reviewers can assist with confidence building. Quality of argument and clarity of presentation in PA will be of key concern. Appropriate tools are required for documenting and tracking assumptions, through a single assessment phase, and between iterative assessment phases. Risks associated with future human actions are of particular concern to the WIPP project, and international consensus on the principles for incorporation of future human actions in assessments would be valuable

  12. Quality Assurance Program Plan for the Waste Isolation Pilot Plant Experimental-Waste Characterization Program

    International Nuclear Information System (INIS)

    1991-01-01

    This Quality Assurance Program Plan (QAPP) identifies the quality of data necessary to meet the specific objectives associated with the Department of Energy (DOE) Waste Isolation Pilot Plant (WIPP) Experimental-Waste Characterization Program (the Program). This experimental-waste characterization program is only one part of the WIPP Test Phase, both in the short- and long-term, to quantify and evaluate the characteristics and behavior of transuranic (TRU) wastes in the repository environment. Other parts include the bin-scale and alcove tests, drum-scale tests, and laboratory experiments. In simplified terms, the purpose of the Program is to provide chemical, physical, and radiochemical data describing the characteristics of the wastes that will be emplaced in the WIPP, while the remaining WIPP Test Phase is directed at examining the behavior of these wastes in the repository environment. 50 refs., 35 figs., 33 tabs

  13. A formal expert judgment procedure for performance assessments of the Waste Isolation Pilot Plant

    Energy Technology Data Exchange (ETDEWEB)

    Trauth, K.M. [Sandia National Labs., Albuquerque, NM (United States); Guzowski, R.V. [Science Applications International Corp., Albuquerque, NM (United States); Hora, S.C. [Univ. of Hawaii, Hilo, HI (United States). Business Administration & Economics Div.

    1994-09-01

    The Waste Isolation Pilot Plant (WIPP) is an experimental facility located in southeastern New Mexico. It has been designed to determine the feasibility of the geologic disposal of defense-generated transuranic waste in a deep bedded-salt formation. The WIPP was also designed for disposal and will operate in that capacity if approved. The WIPP Performance Assessment Department at Sandia National Laboratories has been conducting analyses to assess the long-term performance of the WIPP. These analyses sometimes require the use of expert judgment. This Department has convened several expert-judgment panels and from that experience has developed an internal quality-assurance procedure to guide the formal elicitation of expert judgment. This protocol is based on the principles found in the decision-analysis literature.

  14. Characterization of subjective uncertainty in the 1996 performance assessment for the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    HELTON, JON CRAIG; MARTELL, MARY-ALENA; TIERNEY, MARTIN S.

    2000-01-01

    The 1996 performance assessment (PA) for the Waste Isolation Pilot Plant (WIPP) maintains a separation between stochastic (i.e., aleatory) and subjective (i.e., epistemic) uncertainty, with stochastic uncertainty arising from the possible disruptions that could occur at the WIPP over the 10,000 yr regulatory period specified by the US Environmental Protection Agency (40 CFR 191,40 CFR 194) and subjective uncertainty arising from an inability to uniquely characterize many of the inputs required in the 1996 WIPP PA. The characterization of subjective uncertainty is discussed, including assignment of distributions, uncertain variables selected for inclusion in analysis, correlation control, sample size, statistical confidence on mean complementary cumulative distribution functions, generation of Latin hypercube samples, sensitivity analysis techniques, and scenarios involving stochastic and subjective uncertainty

  15. Pilot plant studies on the extraction of antimony metal from lower grade krinj stibnite ore

    International Nuclear Information System (INIS)

    Rehman, W.; Riaz, M.; Ishaq, M.

    2013-01-01

    Antimony is a silvery white, brittle and crystalline solid which is extensively consumed in lead acid batteries, antimonial lead alloys, flame retardants and a variety of metallic products. The antimony content of commercial ores range from 5-60% and determines the method of extraction, either pyrometallurgical or hydrometallurgical. The present study focuses on pilot plant scale extraction of antimony metal from lower grade stibnite ore of Krinj (Chitral) without the use of iron scrap, thus eliminating the second step of iron removal in conventional direct reduction method. A tilting gas fired furnace with digital temperature control system and a heat recuperator was designed to optimize the operating parameters for extraction of antimony metal. Weight ratios of flux and reductant, operating time and operating temperature were optimized. Highest percentage recovery and purity were achieved using soda ash as a flux, at a temperature of 900 degree C for 2 hours. (author)

  16. Recovery of protactinium-231 and thorium-230 from cotter concentrate: pilot plant operatins and process development

    International Nuclear Information System (INIS)

    Hertz, M.R.; Figgins, P.E.; Deal, W.R.

    1983-01-01

    The equipment and methods used to recover and purify 339 g of thorium-230 and 890 mg of protactinium-231 from 22 of the 1251 drums of Cotter Concentrate are described. The process developed was (1) dissolution at 100 0 C in concentrated nitric acid and dilution to 2 to 3 molar acid, (2) filtration to remove undissolved solids (mostly silica filter aid), (3) extraction of uranium with di-sec-butyl-phenyl phophonate (DSBPP) in carbon tetrachloride, (4) extraction of both thorium and protactinium with tri-n-octylphosphine oxide (TOPO) in carbon tetrachloride followed by selective stripping of the thorium with dilute of sulfuric acid, (5) thorium purification using oxalic acid, (6) stripping protactinium from the TOPO with oxalic acid, and (7) protactinium purification through a sequence of steps. The development of the separation procedures, the design of the pilot plant, and the operating procedures are described in detail. Analytical procedures are given in an appendix. 8 figures, 4 tables

  17. Preliminary experiences with material testing at the oxyfuel pilot plant at Schwarze Pumpe

    Energy Technology Data Exchange (ETDEWEB)

    Hjoernhede, Anders [Vattenfall Power, Gothenborg (Sweden); Montgomery, Melanie [Technical Univ. Denmark, Lyngby (Denmark). Inst. for Mekanisk Teknologi; Vattenfall Heat Nordic, Lyngby (Denmark); Bjurman, Martin; Henderson, Pamela [Vattenfall AB (Sweden). Research and Development; Gerhardt, Alexander [Vattenfall AB, Berlin (Germany). Research and Development

    2010-07-01

    Several material related issues may arise from oxyfuel combustion of coal due to the presence of CO{sub 2} but also as an effect of the partial recirculation of the flue gas. Two examples are increased corrosion and carburisation which may limit steam data, hence limiting the efficiency. A number of corrosion tests, in both conventional air-firing and oxyfuel mode, have been made in Vattenfalls 30 MW oxyfuel pilot plant located in Schwarze Pumpe, Germany. Internally cooled corrosion probes, equipped with ferritic, austenitic, super austenitic steels as well as Ni-based and FeCrAl alloys, simulating superheaters, economisers and air preheaters were exposed for up to 1500 hrs. The analyses show an indication of higher material wastage in oxyfuel compared to air combustion especially at the lower exposure temperatures. This may be due to increased sulphur concentration in corrosion front, increased heat flux, carburisation or other precipitate formations on austenitic steels and Ni-based alloys. (orig.)

  18. Volatile Organic Compound (VOC) Air Monitoring Program design for the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    Frank, L.

    1991-01-01

    The Waste Isolation Pilot Plant (WIPP) Volatile Organic Compound (VOC) Monitoring Program has been developed as part of the Department of Energy's (DOE's) No-Migration Variance petition submitted to the Environmental Protection Agency (EPA). The program is designed to demonstrate that there will be no migration of hazardous chemicals past the unit boundary in concentrations which exceed any health-based standards. The monitoring program will use EPA compendium Method TO-14. Both air and carbon sorption media samples will be collected as part of the program. Eleven separate monitoring sites have been selected where both 24-hour integrated and 1-hour grab samples will be collected and analyzed for five target compounds. The bin-scale experimental test rooms will be configured with a gas collection manifold and an activated carbon sorption bed to remove VOCs before they can be emitted into the WIPP underground atmosphere. 10 refs., 4 figs., 7 tabs

  19. Development of quality assurance and performance testing for the Process Experimental Pilot Plant

    International Nuclear Information System (INIS)

    Dole, L.R.; McDaniel, E.W.; Robinson, S.M.

    1984-08-01

    The Process Experimental Pilot Plant (PREPP) is planned for operation by EG and G Idaho, Inc., to demonstrate a full-scale, cement-based, disposal process for transuranic (TRU) wastes. Procedures need to be developed to determine the quality of the waste product during processing and the durability of the final waste form produced in this facility. This report summarizes basic guidelines for the selection of the waste form composition and process conditions that affect product performance. Physical property tests that may be applicable for quality assurance during processing are also described. Approaches to accelerated performance tests needed to predict the performance of the cement-based waste form are identified, and suggestions are made for the development of processing tests to ensure the quality of the final waste-host product. 29 references, 3 figures, 4 tables

  20. Waste Isolation Pilot Plant disposal phase supplemental environmental impact statement. Implementation plan

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-05-01

    The Implementation Plan for the Waste Isolation Pilot Plant Disposal Phase Supplemental Environmental Impact Statement (SEIS-II) has two primary purposes: (1) To report on the results of the scoping process (2) To provide guidance for preparing SEIS-II SEIS-II will be the National Environmental Policy Act (NEPA) review for WIPP`s disposal phase. Chapter 1 of this plan provides background on WIPP and this NEPA review. Chapter 2 describes the purpose and need for action by the Department of Energy (hereafter DOE or the Department), as well as a description of the Proposed Action and alternatives being considered. Chapter 3 describes the work plan, including the schedule, responsibilities, and planned consultations with other agencies and organizations. Chapter 4 describes the scoping process, presents major issues identified during the scoping process, and briefly indicates how issues will be addressed in SEIS-II.