WorldWideScience
1

Natural-convection cooling of heat-producing radioactive waste in transport and storage casks  

International Nuclear Information System (INIS)

The heat transfer characteristics of a newly developed transport and storage cask for vitrified heat-producing radioactive waste from reprocessing are described. The theoretical layout of the cask was tested by measurements on a prototype cask of the scale 1:1. These measurements confirmed the theoretical thermodynamic layout data. They can be described by the function Nu=CxRa"m, with the constant C, but not the constant m, differing for a vertical and a horizontal position of the cask. The measured velocity and temperature profiles of the cask were verified with an existing code for the calculation of heat transfer from finned horizontal cylinders by natural convection. (orig.).

2

Experience in complying with quality assurance requirements for cask lifting devices  

International Nuclear Information System (INIS)

The Nuclear Assurance Corporation (NAC) owns and operates four NAC-1 truck casks. These casks are used to ship spent reactor fuel assemblies and radioactive reactor-core components. The casks have been loaded or unloaded at a total of fifteen nuclear facilities in the United States. In addition, NAC has used another large, overweight-truck cask to ship radioactive reactor core components from a reactor to a waste burial site. There are many individual differences in the cask handling facilities at each of the reactor stations, nuclear research facilities and the storage and burial sites serviced. Various types of auxiliary lifting and handling devices for on-site cask operations have been required. The quality assurance requirements for the equipment used in interfacing casks with nuclear power plant ...

3

Cost comparison among spent fuel storage techniques  

Energy Technology Data Exchange (ETDEWEB)

Scenarios are developed for spent fuel that is taken out of the nuclear reactor and stored for 20 years before reprocessing, and three storage techniques which use a water pool, dry cask or vault are compared with respect to their costs. The storage price (storage cost per kilogram of spent fuel), which is employed as the economic index, is calculated on the assumption that all the charge is paid when the spent fuel is brought in the storage facilities. Four scenarios are assumed for spent PWR and BWR fuels to be stored in at-reactor (AT) or away-from-reactor (AFR) facilities. The capital costs cover the buildings of the storage facilities, equipment, decommissioning, casks for transportation and storage (for cask storage) and casks for transportation (for ...

1987-09-01

4

Cost comparison among spent fuel storage techniques  

International Nuclear Information System (INIS)

Scenarios are developed for spent fuel that is taken out of the nuclear reactor and stored for 20 years before reprocessing, and three storage techniques which use a water pool, dry cask or vault are compared with respect to their costs. The storage price (storage cost per kilogram of spent fuel), which is employed as the economic index, is calculated on the assumption that all the charge is paid when the spent fuel is brought in the storage facilities. Four scenarios are assumed for spent PWR and BWR fuels to be stored in at-reactor (AT) or away-from-reactor (AFR) facilities. The capital costs cover the buildings of the storage facilities, equipment, decommissioning, casks for transportation and storage (for cask storage) and casks for transportation (for ...

5

FDS3 simulations of indoor hydrocarbon fires engulfing radioactive waste packages  

International Nuclear Information System (INIS)

The thermal environment of a hypothetical large indoor hydrocarbon pool fire is more complex compared to outdoor fires and can be more severe for engulfed objects. In order to analyze potential thermal environments for interim storage of spent fuel casks or low-level radioactive waste packages engulfed in pool fires numerical simulations with the CFD fire code FDS3 were carried out for different storage configurations. In addition, data of indoor pool fire experiments were used to validate the model for this type of application. A series of pool fire experiments under different ventilation conditions and varied pool surface (1 m"2 - 4 m"2) inside a compartment of 3.6 m x 3.6 m x 5.7 m was conducted at iBMB (Institut fuer Baustoffe, Massivbau und Brandschutz) of Braunschweig University of Technology, Germany. The instrumentation included thermocouples, heatflux and pressure gauges, bi-directional flow ...

2004-09-20

6

Time/motion observations of reactor loading, transportation, and dry unloading of an oversized truck spent-fuel shipment  

International Nuclear Information System (INIS)

This paper presents actual time/motion data for an oversize truck spent-fuel shipment from its origin, Surry, Virginia to its destination, Idaho National Engineering Laboratory (INEL). These data include the receipt of the empty cask at the reactor, wet-loading the cask, over-the-road or in-transit data, and receipt and dry unloading of the shipping cask at the receiving facility. Occupational doses were recorded at the Surry Power Plant as well as at INEL, and public doses were calculated for the in-transit dose analysis. This shipment was one of a series performed in support of a demonstration and evaluation of dry storage at INEL. The oversized shipment consisted of a TN-8L shipping cask loaded with three 10-yr-old pressurized water reactor assemblies. The total distance traveled was #approx#2800 miles, requiring 62 h including stops. The time required to receive and inspect the ...

1988-11-04

7

Verification of maximum impact force for interim storage cask for the Fast Flux Testing Facility  

Energy Technology Data Exchange (ETDEWEB)

The objective of this paper is to perform an impact analysis of the Interim Storage Cask (ISC) of the Fast Flux Test Facility (FFTF) for a 4-ft end drop. The ISC is a concrete cask used to store spent nuclear fuels. The analysis is to justify the impact force calculated by General Atomics (General Atomics, 1994) using the ILMOD computer code. ILMOD determines the maximum force developed by the concrete crushing which occurs when the drop energy has been absorbed. The maximum force, multiplied by the dynamic load factor (DLF), was used to determine the maximum g-level on the cask during a 4-ft end drop accident onto the heavily reinforced FFTF Reactor Service Building`s concrete surface. For the analysis, this surface was assumed to be unyielding and the cask absorbed all the drop energy. This conservative assumption simplified the modeling used to qualify the ...

1996-06-01

8

Use of robotics for radioactive waste shipping and receiving  

International Nuclear Information System (INIS)

Radioactive waste shipping and receiving facilities presently planned for commercial and defence high level nuclear waste will handle waste packages at frequencies far in excess of those in common practice today. If current limits for radiation levels at the cask surface and current handling methods are used, high cumulative personnel exposure to ionizing radiation is projected to occur. To reduce these exposure levels, alternate handling methods are being developed and demonstrated. The production nature of cask receiving operations suggests commercial robotics be incorporated into a remote handling system to reduce predicted worker exposure to acceptable levels while maintaining or increasing throughput. The first phase of cask handling system development culminated in a proof-of-principle test demonstrating the feasibility of performing ...

1986-06-16

9

Use of robotics for radioactive waste shipping and receiving  

International Nuclear Information System (INIS)

Radioactive waste shipping and receiving facilities presently planned for commercial and defense high-level nuclear waste will handle waste packages at frequencies far in excess of those in common practice today. If current limits for radiation levels at the cask surface and current handling methods are used, high cumulative personnel exposure to ionizing radiation is projected to occur. To reduce these exposure levels, alternate handling methods are being developed and demonstrated. The production nature of cask receiving operations, suggests commercial robotics be incorporated into a remote handling system to reduce predicted worker exposure to acceptable levels while maintaining or increasing throughput. The first phase of cask handling system development culminated in a proof-of-principle test demonstrating the feasibility of performing ...

1986-06-16

10

Use of commercial robotics in radioactive waste shipping and receiving  

International Nuclear Information System (INIS)

Radioactive waste shipping and receiving facilities presently planned for commercial and defense nuclear waste will handle waste packages at frequencies far in excess of those in common practice today. Unacceptable personnel exposure to ionizing radiation is projected to occur if current limits for radiation levels at the cask surface and current handling methods are used. To reduce these exposure levels, alternate handling methods are being developed and demonstrated. The production nature of cask receiving operations suggests commercial robotics be incorporated into a remote handling system to reduce predicted worker exposure to acceptable levels, while maintaining or increasing throughput. The first phase of cask handling system development culminated in a proof-of-principle test demonstrating the feasibility of performing cask receiving ...

1985-04-21

11

BR-100 spent fuel shipping cask development  

Energy Technology Data Exchange (ETDEWEB)

Continued public acceptance of commercial nuclear power is contingent to a large degree on the US Department of Energy (DOE) establishing an integrated waste management system for spent nuclear fuel. As part of the from-reactor transportation segment of this system, the B W Fuel Company (BWFC) is under contract to the DOE to develop a spent-fuel cask that is compatible with both rail and barge modes of transportation. Innovative design approaches were the keys to achieving a cask design that maximizes payload capacity and cask performance. The result is the BR-100, a 100-ton rail/barge cask with a capacity of 21 PWR or 52 BWR ten-year cooled, intact fuel assemblies. 3 figs.

1990-01-01

12

Disposal of spent fuel from German nuclear power plants - paper work or technology?  

International Nuclear Information System (INIS)

The reference concept 'direct disposal of spent fuel' was developed as an alternative to spent fuel reprocessing and vitrified HLW disposal. The technical facilities necessary for the implementation of this reference concept - the so called POLLUX-concept, e.g. interim storages for casks containing spent fuel, a pilot conditioning facility, and a special cask 'POLLUX' for final disposal have been built. With view to a geological salt formation all handling procedures for the repository were tested aboveground in a test facility at a 1:1 scale. To optimise the concept all operational steps are reviewed for possible improvement. Most promising are a concept using canisters (BSK 3) instead of POLLUX casks, and the direct disposal of transport and storage casks (DIREGT-concept) which is the most recent one and has been designed for the direct disposal of large ...

2006-09-17

13

Cask consolidated spent fuel thermal analyses using the COBRA-SFS code  

Energy Technology Data Exchange (ETDEWEB)

The COBRA-SFS computer code was used to perform thermal-hydraulic analyses of consolidated spent fuel stored in casks. The ability of the COBRA-SFS code to model consolidated fuel was evaluated by comparing predictions with experimental data obtained from electrically heated rod bundles by Ridihalgh, Eggers, and Associates and Eggers Ridihalgh Partners, Inc. under sponsorship of the Electric Power Research Institute. The calculations agreed with the measured temperatures well within the bounds of experimental error. Based on the evaluation results, best-estimate temperature predictions were performed for consolidated fuel in several cask designs. Results are presented for the REA 2023 BWR cask, the CASTOR-1C BWR cask, and the Concrete Sealed Storage Cask designed for Monitored Retrievable Storage (MRS). The cask ...

1986-04-01

14

Dry storage concepts and their thermodynamic layout  

International Nuclear Information System (INIS)

The two favourable dry storage concepts being under consideration in the Federal Republic of Germany are presented and the physical behaviour or natural convection cooling with air is explained. With the three examples cask store, vault storage horizontally and vertically arranged the main thermodynamical design parameters and their influence on the efficiency of the cooling system and on the temperature distribution inside the store and of the stored material are discussed. Moreover, the importance of the fulfilment and the harmony of all safety criteria and the difficulties while to do so are carried out especially with the vault store.

15

Evaluation test on the thermal stability of resin as neutron shielding material for spent fuel transport cask  

Energy Technology Data Exchange (ETDEWEB)

Epoxy-resin based neutron shielding material, NS-4-FR, is used for spent fuel transport and/or storage cask. In this paper the outline of thermal aging test performed to evaluate the heating effect on this neutron shielding material, NS-4-FR, is introduced. The test is consisted of two kinds of thermal aging test, one is 'Basic Test' and the other is 'Block Heating Test'. The former is cooperatively performed by ten Japanese Electrical Power Companies, and the latter is done by GESC and NOF Corporation. (authors)

1998-07-01

16

Evaluation test on the thermal stability of resin as neutron shielding material for spent fuel transport cask  

International Nuclear Information System (INIS)

Epoxy-resin based neutron shielding material, NS-4-FR, is used for spent fuel transport and/or storage cask. In this paper the outline of thermal aging test performed to evaluate the heating effect on this neutron shielding material, NS-4-FR, is introduced. The test is consisted of two kinds of thermal aging test, one is 'Basic Test' and the other is 'Block Heating Test'. The former is cooperatively performed by ten Japanese Electrical Power Companies, and the latter is done by GESC and NOF Corporation. (authors)

1998-05-10

17

Waste Food Storage at Fortress Rocks  

Science.gov (United States)

... of waste food generated at McMurdo Station. Some of the difficulties of disposing of waste food ... change waste generation or management at the site? Yes. This will be a temporary waste management ...

18

Waste management considerations for fusion power reactors  

International Nuclear Information System (INIS)

To estimate the waste management needs of a fusion power reactor, a scheme for handling radioactive waste from a fusion plant has been devised. The handling scheme proceeds with radioactive waste, primarily from blanket replacement, being stored on-site; waste in cooled and shielded casks is then isolated off-site; finally, the materials are recycled. Using activities and component lifetimes supplied by designers, several conceptual fusion power reactors have been analyzed and their waste streams compared to fission reactors with regard to total activity, specific activity, and lifetimes of activity.

19

Waste management considerations for fusion power reactors  

Science.gov (United States)

To estimate the waste management needs of a fusion power reactor, a scheme for handling radioactive waste from a fusion plant has been devised. The handling scheme proceeds with radioactive waste, primarily from blanket replacement, being stored on-site; waste in cooled and shielded casks is then isolated off-site; finally, the materials are recycled. Using activities and component lifetimes supplied by designers, several conceptual fusion power reactors have been analyzed and their waste streams compared to fission reactors with regard to total activity, specific activity, and lifetimes of activity.

1978-02-01

20

Overview of the FRG waste package materials corrosion test program  

International Nuclear Information System (INIS)

Presently in the FRG there are essentially three institutions involved in corrosion experiments related to high level waste package materials, namely KfK-INE, Nukem and Bayer Leverkusen. In 1981 KfK-INE started a corrosion test program aiming at the selection of suitable canister materials for vitrified high level waste. The program encompassed electrochemical investigations, which were concluded in 1984. Moreover field corrosion tests and laboratory experiments were initiated, and are still ongoing. Several possible canister materials such as mild steel, Ti-Pd-alloy, Hastelloy C4 and others were investigated under the influence of varying parameters such as temperature, and radiation. Both Nukem Company and DWK were assigned the responsibility to conceive and develop a cask for the direct final disposal of spent fuel assemblies. Two solution turned out as most promising for corrosion protection of final disposal ...

1988-03-08

21

Safety analysis practices for the dense storage of RBMK spent fuel and improved technology for the long term storage of spent fuel in water pools  

International Nuclear Information System (INIS)

The paper discusses the safety problems connected with the conversion to dense storage of RBMK-1000 spent fuel in reactor cooling pools and independent storage facilities. Recourse to dense storage has been made for a number of reasons, among which are the absence of spent fuel shipments from the nuclear power plant site, prolongation of storage time and a partial change in storage conditions. Increasing the storage density per unit volume of the storage facility and turning to new technical procedures (as against the basic design) call for further investigation of safety problems. The safety assessment of the dense storage mode includes: (1) Selecting a list of initiating events for design basis and unforeseeable accidents; (2) Assessing dense storage safety under normal as well as design basis ...

1995-08-01

22

Transportation cask decontamination and maintenance at the potential Yucca Mountain repository; Yucca Mountain Site characterization project  

Energy Technology Data Exchange (ETDEWEB)

This study investigates spent fuel cask handling experience at existing nuclear facilities to determine appropriate cask decontamination and maintenance operations at the potential Yucca Mountain repository. These operations are categorized as either routine or nonroutine. Routine cask decontamination and maintenance tasks are performed in the cask preparation area at the repository. Casks are taken offline to a separate cask maintenance area for major nonroutine tasks. The study develops conceptual designs of the cask preparation area and cask maintenance area. The functions, layouts, and major features of these areas are also described.

1992-04-01

23

CONVERTING WASTE  

Wastenet

condenser, gas refiner, oil (gas) storage tank and dual fuel engine

24

Spent fuel transportation cask response to a tunnel fire scenario  

Energy Technology Data Exchange (ETDEWEB)

On July 18, 2001, a freight train carrying hazardous (non-nuclear) materials derailed and caught fire while passing through the Howard Street railroad tunnel in downtown Baltimore, Maryland. The United States Nuclear Regulatory Commission (USNRC), one of the agencies responsible for ensuring the safe transportation of radioactive materials in the United States, undertook an investigation of the train derailment and fire to determine the possible regulatory implications of this particular event for the transportation of spent nuclear fuel by railroad. Shortly after the accident occurred, the USNRC met with the National Transportation Safety Board (NTSB), the U.S. agency responsible for determining the cause of transportation accidents, to discuss the details of the accident and the ensuing fire. Following these discussions, the USNRC assembled a team of experts from the National Institute of Standards and Technology (NIST), the Center for Nuclear Waste Regulatory ...

2004-07-01

25

Initiation of depleted uranium oxide and spent fuel testing for the spent fuel sabotage aerosol ratio programme  

Energy Technology Data Exchange (ETDEWEB)

We provide a detailed overview of an on-going, multinational test programme that is developing aerosol data for some spent fuel sabotage scenarios on spent fuel transport and storage casks. Experiments are being performed to quantify the aerosolised materials plus volatilised fission products generated from actual spent fuel and surrogate material test rods, due to impact by a high-energy/density device. The programme participants in the United States plus Germany, France and the United Kingdom, part of the international Working Group for Sabotage Concerns of Transport and Storage Casks (WGSTSC) have strongly supported and coordinated this research programme. Sandia National Laboratories has the lead role for conducting this research programme; test programme support is provided by both the US Department of Energy and the US Nuclear Regulatory Commission. We provide a summary of the overall, multiphase ...

2004-07-01

26

Initiation of depleted uranium oxide and spent fuel testing for the spent fuel sabotage aerosol ratio programme  

International Nuclear Information System (INIS)

We provide a detailed overview of an on-going, multinational test programme that is developing aerosol data for some spent fuel sabotage scenarios on spent fuel transport and storage casks. Experiments are being performed to quantify the aerosolised materials plus volatilised fission products generated from actual spent fuel and surrogate material test rods, due to impact by a high-energy/density device. The programme participants in the United States plus Germany, France and the United Kingdom, part of the international Working Group for Sabotage Concerns of Transport and Storage Casks (WGSTSC) have strongly supported and coordinated this research programme. Sandia National Laboratories has the lead role for conducting this research programme; test programme support is provided by both the US Department of Energy and the US Nuclear Regulatory Commission. We provide a summary of the overall, multiphase ...

27

Initiation of depleted uranium oxide and spent fuel testing for the spent fuel sabotage aerosol ratio program.  

Energy Technology Data Exchange (ETDEWEB)

The authors provide a detailed overview of an on-going, multinational test program that is developing aerosol data for some spent fuel sabotage scenarios on spent fuel transport and storage casks. Experiments are being performed to quantify the aerosolized materials plus volatilized fission products generated from actual spent fuel and surrogate material test rods, due to impact by a high-energy-density device. The program participants in the United States plus Germany, France and the United Kingdom, part of the international Working Group for Sabotage Concerns of Transport and Storage Casks (WGSTSC) have strongly supported and coordinated this research program. Sandia National Laboratories has the lead role for conducting this research program; test program support is provided by both the US Department of Energy and the US Nuclear Regulatory Commission. The authors provide a summary of the overall, ...

2004-08-01

28

Initiation of depleted uranium oxide and spent fuel testing for the spent fuel sabotage aerosol ratio program  

International Nuclear Information System (INIS)

The authors provide a detailed overview of an on-going, multinational test program that is developing aerosol data for some spent fuel sabotage scenarios on spent fuel transport and storage casks. Experiments are being performed to quantify the aerosolized materials plus volatilized fission products generated from actual spent fuel and surrogate material test rods, due to impact by a high-energy-density device. The program participants in the United States plus Germany, France and the United Kingdom, part of the international Working Group for Sabotage Concerns of Transport and Storage Casks (WGSTSC) have strongly supported and coordinated this research program. Sandia National Laboratories has the lead role for conducting this research program; test program support is provided by both the US Department of Energy and the US Nuclear Regulatory Commission. The authors provide a summary of the overall, ...

29

Installation Restoration Program. Stage 3. McClellan Air Force ...  

Science.gov (United States)

... pits, waste oil and solvent storage ponds (used from the 1940s to 1971), surface storage areas, settling ponds, waste water ponds, and unlined ...

1990-03-01

30

FIELD CORROSION TESTS IN REDOX AND PUREX UNDERGROUND WASTE STORAGE TANKS  

Science.gov (United States)

A corrosion-testing program has been initiated in Purex and Redox storage tnnks to obtain corrosion data on carbon steel and three associated materials in neutralized process wastes. (C.W.H.)

1955-06-28

31

Feasibility study on scheme of disposing spent guide tubes at Daya Bay nuclear power plant  

International Nuclear Information System (INIS)

The author describes feasibility study on the scheme of disposing spent guide tubes at Daya Bay nuclear power plant, including scheme selection, packing cask design, disposal operation and technological process, budget estimation and safety evaluation. The research results show that the new scheme is feasible on technology, and reasonable on budget. If the scheme is adopted to dispose the spent guide tubes at Daya Bay nuclear power station, it can not only save large funds, but also accumulate experience on disposing non-compressible low and intermediate level solid radioactive wastes produced at nuclear power station for the country

1998-12-01

32

Spent fuel sabotage aerosol ratio program : FY 2004 test and data summary  

International Nuclear Information System (INIS)

This multinational, multi-phase spent fuel sabotage test program is quantifying the aerosol particles produced when the products of a high energy density device (HEDD) interact with and explosively particulate test rodlets that contain pellets of either surrogate materials or actual spent fuel. This program has been underway for several years. This program provides data that are relevant to some sabotage scenarios in relation to spent fuel transport and storage casks, and associated risk assessments. The program also provides significant technical and political benefits in international cooperation. We are quantifying the Spent Fuel Ratio (SFR), the ratio of the aerosol particles released from HEDD-impacted actual spent fuel to the aerosol particles produced from surrogate materials, measured under closely matched test conditions, in a contained test chamber. In addition, we are measuring the amounts, nuclide content, size distribution of the ...

33

The Need for Confirmatory Experiments on the Radioactive Source Term from Potential Sabotage of Spent Nuclear Fuel Casks  

Science.gov (United States)

A technical review is presented of experiment activities and state of knowledge on air-borne, radiation source terms resulting from explosive sabotage attacks on spent reactor fuel subassemblies in shielded casks. Current assumptions about the behavior of irradiated fuel are largely based on a limited number of experimental results involving unirradiated, depleted uranium dioxide ''surrogate'' fuel. The behavior of irradiated nuclear fuel subjected to explosive conditions could be different from the behavior of the surrogate fuel, depending on the assumptions made by the evaluator. Available data indicate that these potential differences could result in errors, and possible orders-of-magnitude overestimates of aerosol dispersion and potential health effects from sabotage attacks. Furthermore, it is suggested that the current assumptions used in arriving at existing regulations for the transportation and ...

2002-04-01

34

Nuclear power plant liquid waste solidification system. [Japan  

Energy Technology Data Exchange (ETDEWEB)

The fundamental points to be considered in a waste treatment system for a country like Japan, where the final disposal method has not been decided and the wastes have to be stored in the power plants, are volume reduction of the wastes, safe storage of the wastes in the plant, and flexibility regarding the final disposal. A system has been developed that consists of a thin film evaporator for the direct solidification of the liquid waste, a pelletizer for producing hard pellets from the powdered wastes, a pellet storage unit, and a solidification unit for the final disposal. A pilot plant with waste treatment capacity of 200 kg/h was built in 1976 and has proved the system feasibility. This paper reports on pilot plant tests of the thin film evaporator and other components, tests on pellet ...

1981-01-01

35

Nuclear power plant liquid waste solidification system  

International Nuclear Information System (INIS)

The fundamental points to be considered in a waste treatment system for a country like Japan, where the final disposal method has not been decided and the wastes have to be stored in the power plants, are volume reduction of the wastes, safe storage of the wastes in the plant, and flexibility regarding the final disposal. A system has been developed that consists of a thin film evaporator for the direct solidification of the liquid waste, a pelletizer for producing hard pellets from the powdered wastes, a pellet storage unit, and a solidification unit for the final disposal. A pilot plant with waste treatment capacity of 200 kg/h was built in 1976 and has proved the system feasibility. This paper reports on pilot plant tests of the thin film evaporator and other components, tests on pellet ...

1981-02-26

36

Response of a Spent Fuel Transportation Cask to a Tunnel Fire Event  

Energy Technology Data Exchange (ETDEWEB)

The staff of the Spent Fuel Project Office at the U.S. Nuclear Regulatory Commission undertook the investigation and thermal analysis of the Baltimore tunnel fire event. This event occurred in the Howard Street tunnel, in Baltimore, Maryland, on July 18, 2001. The staff was tasked with assessing the consequences of this event on the transportation of spent nuclear fuel. This paper describes the staff's coordination with the following government and laboratory organizations: the National Transportation Safety Board (NTSB), to determine the details of the train derailment and fire; the National Institute of Standards and Technology (NIST), to quantify the thermal conditions within the tunnel; the Center for Nuclear Waste Regulatory Analysis (CNWRA), to validate the NIST evaluations, and the Pacific Northwest National Laboratory (PNNL), to assist in the thermal analysis. The results of the staff's review and analysis efforts are also discussed. The ...

2003-02-25

37

Evaluation of the Cask Transportation Facility Modifications (CTFM) compliance to DOE order 6430.1A; FINAL  

International Nuclear Information System (INIS)

This report was prepared to evaluate the compliance of Cask Transportation Facility Modifications (CTFM) to DOE Order 6430.1A.

38

Present State of Radioactive Waste Management and Treatment Technology at the Research Centre Seibersdorf  

International Nuclear Information System (INIS)

Since 1976 the Austrian Research Centre Seibersdorf has the task to collect, treat and store radioactive waste (Radwaste) arising in Austria. Within the Department of Waste Management a variety of appropriate treatment systems are installed. For storing unconditioned and conditioned waste proper storage-halls are available. The collection of Radwaste is carried out using 100 l drums, for the conditioned waste the 200 l drum concept is used. The interim storage of conditioned waste is done at Seibersdorf until a final repository is built. The present plan foresees one to be in operation at the year 2012. (author).

1996-10-07

39

Waste Management Project fiscal year 1998 multi-year work plan, WBS 1.2  

Energy Technology Data Exchange (ETDEWEB)

The Waste Management Project manages and integrates (non-TWRS) waste management activities at the site. Activities include management of Hanford wastes as well as waste transferred to Hanford from other DOE, Department of Defense, or other facilities. This work includes handling, treatment, storage, and disposal of radioactive, nonradioactive, hazardous, and mixed solid and liquid wastes. Major Waste Management Projects are the Solid Waste Project, Liquid Effluents Project, and Analytical Services. Existing facilities (e.g., grout vaults and canyons) shall be evaluated for reuse for these purposes to the maximum extent possible.

1997-09-23

40

Emplacement technology for the direct disposal of spent fuel into deep vertical boreholes  

International Nuclear Information System (INIS)

In the early sixties it was decided to investigate salt formations on its suitability to host heat generating radioactive waste in Germany. In the reference repository concept consequently the emplacement of vitrified waste canisters in deep vertical boreholes inside a salt mine was considered whereas spent fuel should be disposed of in self shielding casks (type POLLUX) in horizontal drifts. The POLLUX casks, 65 t heavy carbon steel casks, will be laid down on the floor of a horizontal drift in one of the disposal zones to be constructed in the salt dome at the 870 m level. The space between casks and drift walls will be backfilled with crushed salt. The transport, the handling und the emplacement of POLLUX casks were subject of successfully performed demonstration and in situ tests in the nineties and resulted in an adjustment of the ...

2008-09-01

41

Initiation of depleted uranium oxide and spent fuel testing for the spent fuel sabotage aerosol ratio program  

Energy Technology Data Exchange (ETDEWEB)

We provide a detailed overview of an ongoing, multinational test program that is developing aerosol data for some spent fuel sabotage scenarios on spent fuel transport and storage casks. Experiments are being performed to quantify the aerosolized materials plus volatilized fission products generated from actual spent fuel and surrogate material test rods, due to impact by a high energy density device, HEDD. The program participants in the U.S. plus Germany, France, and the U.K., part of the international Working Group for Sabotage Concerns of Transport and Storage Casks, WGSTSC have strongly supported and coordinated this research program. Sandia National Laboratories, SNL, has the lead role for conducting this research program; test program support is provided by both the U.S. Department of Energy and Nuclear Regulatory Commission. WGSTSC partners need this research to better understand potential ...

2004-07-01

42

The Los Alamos National Laboratory Transuranic Waste Retireval Project  

Energy Technology Data Exchange (ETDEWEB)

This paper presents the status of the Los Alamos National Laboratory (LANL) project for remediation of transuranic (TRU) and TRU mixed waste from Pads 1, 2, and 4. Some of the TRU waste packages retrieved from Pad I are anticipated to be part of LANL`s initial inventory to be shipped to the Waste Isolation Pilot Plant (WIPP) in April 1998. The TRU Waste Inspectable Storage Project (TWISP) was initiated in February 1993 in response to the New Mexico Environment Department`s (NMED`s) Consent Agreement for Compliance Order, ``New Mexico Hazardous Waste Agreement (NMHWA) 93-03.`` The TWISP involves the recovery of approximately 16,865 TRU and TRU-mixed waste containers currently under earthen cover on Pads 1, 2, and 4 at Technical Area 54, Area G, and placement of that waste into inspectable storage. All ...

1997-02-01

43

An online monitoring system for nuclear waste storage  

International Nuclear Information System (INIS)

We propose a system for the on-line monitoring of short and medium term radioactive waste repositories. Such a system is distributed, fine-grained, robust, reliable, and must be based on low-cost components. It could, in principle, open new perspectives on the modality of waste packaging and storage. In particular we propose to employ a new family of cheap and powerful micro sensors to be placed in shape of a fine grid around each single drum. (authors)

2009-06-07

44

Hanford Waste Management Plan, 1987  

Energy Technology Data Exchange (ETDEWEB)

The purpose of the Hanford Waste Management Plan (HWMP) is to provide an integrated plan for the safe storage, interim management, and disposal of existing waste sites and current and future waste streams at the Hanford Site. The emphasis of this plan is, however, on the disposal of Hanford Site waste. The plans presented in the HWMP are consistent with the preferred alternative which is based on consideration of comments received from the public and agencies on the draft Hanford Defense Waste Environmental Impact Statement (HDW-EIS). Low-level waste was not included in the draft HDW-EIS whereas it is included in this plan. The preferred alternative includes disposal of double-shell tank waste, retrievably stored and newly generated TRU waste, one pre-1970 TRU solid waste site ...

1987-01-01

45

Savannah River Site Interim Waste Management Program Plan FY 1991--1992  

Energy Technology Data Exchange (ETDEWEB)

The primary purpose of the Waste Management Program Plan is to provide an annual report of how Waste Management's operations are conducted, what facilities are being used to manage wastes, what forces are acting to change current waste management systems, and what plans are in store for the coming fiscal year. In addition, this document projects activities for several years beyond the coming fiscal year in order to adequately plan for safe handling, storage, and disposal of radioactive wastes generated at the Savannah River Site and for developing technology for improved management of wastes. In this document, work descriptions and milestone schedules are current as of December 1991.

1992-05-01

46

RH-TRU Waste Inventory Characterization by AK and Proposed WIPP RH-TRU Waste Characterization Objectives  

Energy Technology Data Exchange (ETDEWEB)

The U.S. Department of Energy (DOE)-Carlsbad Field Office (CBFO) has developed draft documentation to present the proposed Waste Isolation Pilot Plant (WIPP) remote-handled (RH-) transuranic (TRU) waste characterization program to its regulators, the U.S. Environmental Protection Agency and the New Mexico Environment Department. Compliance with Title 40, Code of Federal Regulations, Parts 191 and 194; the WIPP Land Withdrawal Act (PL 102-579); and the WIPP Hazardous Waste Facility Permit, as well as the Certificates of Compliance for the 72-B and 10-160B Casks, requires that specific waste parameter limits be imposed on DOE sites disposing of TRU waste at WIPP. The DOE-CBFO must control the sites' compliance with the limits by specifying allowable characterization methods. As with the established WIPP contact handled TRU waste ...

2002-02-26

48

Compatibility analysis of DUPIC fuel (part 3) - radiation physics analysis  

International Nuclear Information System (INIS)

As a part of the compatibility analysis of DUPIC fuel in CANDU reactors, the radiation physics calculations have been performed for the CANDU primary shielding system, thermal shield, radiation damage, transportation cask and storage. At first, the primary shield system was assessed for the DUPIC fuel core, which has shown that the dose rates and heat deposition rates through the primary shield of the DUPIC fuel core are not much different from those of natural uranium core because the power levels on the core periphery are similar for both cores. Secondly, the radiation effects on the critical components and the themal shields were assessed when the DUPIC fuel is loaded in CANDU reactors. Compared with the displacement per atom (DPA) of the critical component for natural uranium core, that for the DUPIC fuel core was increased by -30% for the innermost groove and the weld points and by -10% for the corner of the calandria subshells and annular ...

2009-07-01

49

Waste management facilities cost information for hazardous waste. Revision 1  

Energy Technology Data Exchange (ETDEWEB)

This report contains preconceptual designs and planning level life-cycle cost estimates for managing hazardous waste. The report`s information on treatment, storage, and disposal modules can be integrated to develop total life-cycle costs for various waste management options. A procedure to guide the US Department of Energy and its contractor personnel in the use of cost estimation data is also summarized in this report.

1995-06-01

50

Strategic planning for waste management: Characterization of chemically and radioactively hazardous waste and treatment, storage, and disposal capabilities for diverse and varied multisite operations  

Energy Technology Data Exchange (ETDEWEB)

Information about current and projected waste generation as well as available treatment, storage, and disposal (TSD) capabilities and needs is crucial for effective, efficient, and safe waste management. This is especially true for large corporations that are responsible for multisite operations involving diverse and complex industrial processes. Such information is necessary not only for day-to-day operations, but also for strategic planning to ensure safe future performance. This paper reports on some methods developed and successfully applied to obtain requisite information and to assist waste management planning at the corporate level in a nationwide system of laboratories and industries. Waste generation and TSD capabilities at selected US Department of Energy (DOE) sites were studied. 1 ref., 2 tabs.

1988-01-01

51

High-level waste storage tank farms/242-A evaporator Standards/Requirements Identification Document (S/RID), Volume 2  

Energy Technology Data Exchange (ETDEWEB)

The High-Level Waste Storage Tank Farms/242-A Evaporator Standards/Requirements Document (S/RID) is contained in multiple volumes. This document (Volume 2) presents the standards and requirements for the following sections: Quality Assurance, Training and Qualification, Emergency Planning and Preparedness, and Construction.

1994-04-01

52

Neptunium storage at Hanford  

Energy Technology Data Exchange (ETDEWEB)

A decision must be made regarding whether the United State`s stockpile of neptunium should be discarded into the waste stream or kept for the production of Pu-238. Although the cost of long term storage is not inconsequential, to dispose of the material means the closing of our option to maintain control over our Pu-238 stockpile. Within the Fuels and Materials Examination Facility at Hanford there exists a remotely operated facility that can be converted for neptunium storage. This paper describes the facility and the anticipated handling requirements.

1993-06-01

53

Logistics modeling of future solid waste storage, treatment, and disposal  

Energy Technology Data Exchange (ETDEWEB)

Logistics modeling is a powerful analytical technique for effective planning of waste storage, treatment, and disposal activities. Logistics modeling facilitates analyses of alternate scenarios for future waste flows, facility schedules, and processing or handling capacities. These analyses provide an increased understanding of the specific needs for waste storage, treatment, and disposal while adequate time remains to plan accordingly. They also help to determine the sensitivity of these needs to various system parameters. This paper discusses a logistics modeling system developed by the Pacific Northwest Laboratory (PNL) to aid in solid waste planning for a large industrial complex managing many different types and classifications of waste. The basic needs for such a system are outlined, and the approach adopted in developing the system is ...

1993-11-01

54

High-level waste canister storage final design, installation, and testing. Topical report  

Energy Technology Data Exchange (ETDEWEB)

This report is a description of the West Valley Demonstration Project`s radioactive waste storage facility, the Chemical Process Cell (CPC). This facility is currently being used to temporarily store vitrified waste in stainless steel canisters. These canisters are stacked two-high in a seismically designed rack system within the cell. Approximately 300 canisters will be produced during the Project`s vitrification campaign which began in June 1996. Following the completion of waste vitrification and solidification, these canisters will be transferred via rail or truck to a federal repository (when available) for permanent storage. All operations in the CPC are conducted remotely using various handling systems and equipment. Areas adjacent to or surrounding the cell provide capabilities for viewing, ventilation, and equipment/component access.

1998-04-01

55

The control of radioactive wastes and the quality assurance requirements  

International Nuclear Information System (INIS)

For prolonged storage and eventual disposal radioactive wastes will be solidified to reduce the problems which accompany liquid waste whilst solid wastes will be encapsulated in an immobilising matrix. In the solidification and encapsulation process it will be important to produce a material in a form which is chemically stable, mechanically strong and which will not react with or allow free passage of groundwater. To this end a continuous check will be required to ensure that the various wastes are chemically compatible with the solidifying and binding matrices and that the associated processes are performed against a strict Quality Programme. The Quality Programme will be extensive requiring the specification of procedures for assessing the quality and nature of the wastes, the detailed operation of the solidification and/or encapsulation, the overpack ...

56

Waste management systems model for energy systems sites on the Oak Ridge Reservation  

Energy Technology Data Exchange (ETDEWEB)

There is a model on the Oak Ridge Reservation which provides requirements for determining capacities and capabilities related to low-level, hazardous, and mixed wastes. In FY 1987, the model will be sufficiently advanced to provide various waste management scenarios. These scenarios will be compared technically, operationally, and financially by use of waste characterization data and process simulators that are currently under development. The results of the process simulations will be used to help identify waste treatment, storage, and disposal technologies that need to be demonstrated prior to full-scale development for DOE use. The information derived from this effort will be made available to all DOE facilities.

1986-01-01

57

PFP dangerous waste training plan  

Science.gov (United States)

This document establishes the minimum training requirements for the Plutonium Finishing Plant (PFP) personnel who are responsible for management of dangerous waste. The training plan outlines training requirements for handling of solid dangerous waste during generator accumulation and liquid dangerous waste during treatment and storage operations. The implementation of this training plan will ensure the PFP facility compliance with the training plan requirements of Dangerous Waste Regulation. Chapter 173-303-330. Washington Administrative Code (WAC). The requirements for such compliance is described in Section 11.0 of WHC-CM-7-5 Environmental Compliance Manual.

1996-01-01

58

Material-not-categorized-as-waste survey for 1992  

Energy Technology Data Exchange (ETDEWEB)

In October 1992, the US Department of Energy, Richland Field Office (RL) requested that Westinghouse Hanford Company (WHC) respond to a letter from EM-331 asking for completion of a survey of items in storage but not categorized as waste (Roberts 1992). The letter contained an attachment with instructions on how to fill out the attached form and what to exclude from the survey (Appendix A). This report is a summary of the information from the response issued to RL. This report primarily is for use in estimating future waste volumes that may have been overlooked because of the nature of their classification as material not categorized as waste (MNCAW) (i.e., not yet declared Waste).

1993-07-01

59

Mastery of risks: we build the memory of radioactive waste disposal facilities  

International Nuclear Information System (INIS)

The ANDRA, the French national agency of radioactive wastes, is organizing today the information needs of tomorrow. The aim is to allow the future generations to have access to the knowledge of the existence of subsurface radioactive waste facilities and to understand the context and technologies of such facilities. The storage of this information is made on 'permanent paper', a high resistant paper with a lifetime of 600 to 1000 years. An updating of these data is made every 5 years for each waste disposal center. Another project, still in progress, concerns the memory management of deep geologic waste disposal facilities for which the time scale to be considered is of the order of millennia. (J.S.)

60

Aqueous radioactive waste bituminization  

International Nuclear Information System (INIS)

The bituminzation of decontamination and ion exchange resin stripping wastes with four grades of asphalt was investigated to determine the effects of asphalt type on the properties of the final products. All waste forms deformed readily under light loads indicating they would flow if not restrained. It was observed in all cases that product leaching rates increased as the hardness of the asphalt used to treat the waste increased. If bituminization is adopted for any Ontario Hydro aqueous radioactive wastes they should be treated with soft asphalt to obtain optimum leaching resistance and mechanical stability during interim storage should be provided by a corrosion resistant container.

5049-01-01

61

Compaction of salt by means of explosives  

Energy Technology Data Exchange (ETDEWEB)

One of the concerns with locating radioactive waste storage sites in salt deposits is how to permanently seal the underground storage areas once they have reached their storage capacity. The compaction of salt using explosives has been identified as a potential method of producing permanent seals in both entryways and shafts to storage areas. This paper describes the test procedure and results of a preliminary investigation to determine the feasibility of utilizing explosives in the compaction of salt. Three simple tests were carried out to measure the degree to which loose salt could be compacted.

1996-12-01

62

Design and procurement report for the FFTF fuel handling systems bottom-loading transfer cask  

International Nuclear Information System (INIS)

The Fast Flux Test Facility (FFTF) bottom-loading transfer cask (BLTC) system is designed to provide ex-vessel fuel transfers of irradiated reactor components between the reactor containment building and the LMFBR shipping cask in the reactor service building. This system is being procured from National Lead Industries, Wilmington, Delaware, under management of Aerojet Manufacturing Company.

1975-11-16

63

Long-term storage of Greater-Than-Class C Low-Level Waste  

Energy Technology Data Exchange (ETDEWEB)

Under Federal law, the Department of Energy (DOE) is responsible for safe disposal of Greater-Than-Class C Low-Level Waste (GTCC LLW) generated by licenses of the Nuclear Regulatory commission (NRC) or Agreement States. Such waste must be disposed of in a facility licensed by the NRC. It is unlikely that licensed disposal of GTCC LLW will be available prior to the year 2010. Pending availability of disposal capacity, DOE is assessing the need for collective, long-term storage of GTCC LLW. Potential risks to public health and safety caused by long-term storage of GTCC LLW at the place of generation will be evaluated to determine if alternative facilities are warranted. If warranted, several options will be investigated to determine the preferred alternative for long-term storage. These options include modification of an existing DOE facility, development of a new DOE facility, or ...

1990-01-01

64

Feasibility of subcriticality and NDA measurements for spent fuel by frequency analysis techniques with {sup 252}Cf  

Energy Technology Data Exchange (ETDEWEB)

The {sup 252}Cf-source-driven frequency analysis method can be used for measuring the subcritical neutron multiplication factor of arrays of LWR fuel and as little as a single PWR fuel assembly. These measurements can be used to verify the criticality safety margins of spent LWR fuel configurations and thus could be a means of obtaining the information to justify burnup credit for spent LWR transportation/storage casks. In addition, the data can be used to validate calculational methods for criticality safety. These measurements provide parameters that have a higher sensitivity to changes in fissile mass than neutron multiplication factor and thus serve as a better test of calculational methods. The analysis have also shown that measurement of the cross power spectral density (CPSD) between detectors on one side of a single fuel assembly and an internal or external {sup 252}Cf source driving the fission chain multiplication process can be used ...

1996-05-01

65

Deployment Scenarios for Nuclear Waste Management  

International Nuclear Information System (INIS)

A major objective of the DOE Advanced Fuel Cycle Initiative, AFCI, is to explore technologies that may reduce the long-term environmental burden of nuclear energy through more efficient disposal of waste materials. In this work, the potential impact of the AFCI technology and its beneficial effects on waste management and its ability to meet waste management objectives are demonstrated. In addition, practical scenarios to improve permanent disposal utilization and/or reduce the temporary spent nuclear fuel (SNF) storage inventory by closing the fuel cycle through transition to fast reactor (FR) converters are also discussed. (authors)

66

Defense Waste and Environmental Restoration Program Plan: Defense Waste Management Division  

Energy Technology Data Exchange (ETDEWEB)

The DEFENSE WASTE MANAGEMENT PROGRAM has been chartered by the Department of Energy (DOE) to receive, reduce, store, and maintain all radioactive defense waste generated by Hanford and received from offsite DOE contractors in a safe condition and in accordance with DOE and Westinghouse Hanford Company (WHC) standards. These activities are accomplished through the use of TRU retrievable storage sites, solid waste burial grounds, liquid waste storage tanks, capsule storage pools, and other low-level waste disposal methods. Continuous and/or periodic surveillance is maintained. Through the use of improved packaging methods, evaporator-crystallization and capsule production waste has been and continues to be put in a safe and economic storage condition pending future reprocessing or ...

1988-09-01

67

TOXICITY OF AROMATIC AEROBIC BIOTRANSFORMATION PRODUCTS OF TOLUENE TO HELA CELLS  

Science.gov (United States)

Petroleum contamination of groundwater is widely recognized as a serious environmental problem. Toluene (methylbenzene) occurs naturally in crude oil and is commonly found as a contaminant in the subsurface as a result of waste disposal and storage activities. Biological transf...

68

Status and progress in sludge washing: A pivotal pretreatment method  

Energy Technology Data Exchange (ETDEWEB)

Separation of the bulk soluble chemical salts from the insoluble metal hydroxides and radionuclides is central to the strategy of disposing Hanford tank waste. Sludge washing and caustic leaching have been selected as the primary methods for processing the 230 million L (61,000,000 gal) of Hanford tank waste. These processes are very similar to those selected for processing waste at the West Valley Site in New York and the Savannah River Site in South Carolina. The purpose of sludge washing is to dissolve and remove the soluble salts in the waste. Leaching of the insoluble solids with caustic will be used to dissolve aluminum hydroxide and chromium hydroxide, and convert insoluble bismuth phosphate to soluble phosphate. The waste will be separated into a high-level solids fraction and a liquid fraction that can be disposed of as low-level waste after cesium ...

1995-01-01

69

Quality assurance requirements for high-level waste form production  

International Nuclear Information System (INIS)

The Department of Energy has issued a Quality Assurance (QA) specification for organizations involved in making a canistered high-level waste form product that is acceptable for storage in a deep geologic federal repository. The logic for the waste form acceptance process is described. In addition to NQA-1 requirements, fourteen supplemental QA requirements have been drafted to fit the waste form production process. A review plan for assuring complicance with the QA specification is provided. Guidelines for preparation of a waste form producer QA program are also presented. It is expected that the QA program description that result will be influential in supporting the acceptybility of the product to OCRWM and for ultimate disposal of the high-level waste in a deep geologic repository. (author) 3 figs., 4 refs.

70

Nuclear waste treatment program: Annual report for FY 1987  

Energy Technology Data Exchange (ETDEWEB)

Two of the US Department of Energy's (DOE) nuclear waste management-related goals are to ensure that waste management is not an obstacle to the further development of light-water reactors and the closure of the nuclear fuel cycle and to fulfill its institutional responsibility for providing safe storage and disposal of existing and future nuclear wastes. As part of its approach to achieving these goals, the Office of Remedial Action and Waste Technology of DOE established what is now called the Nuclear Waste Treatment Program (NWTP) at the Pacific Northwest Laboratory during the second half of FY 1982. To support DOE's attainment of its goals, the NWTP is to provide technology necessary for the design and operation of nuclear waste treatment facilities by commercial enterprises as part of a licensed ...

1988-09-01

71

DWPF waste form compliance plan (Draft Revision)  

Energy Technology Data Exchange (ETDEWEB)

The Department of Energy currently has over 100 million liters of high-level radioactive waste in storage at the Savannah River Site (SRS). In the late 1970's, the Department of Energy recognized that there were significant safety and cost advantages associated with immobilizing the high-level waste in a stable solid form. Several alternative waste forms were evaluated in terms of product quality and reliability of fabrication. This evaluation led to a decision to build the Defense Waste Processing Facility (DWPF) at SRS to convert the easily dispersed liquid waste to borosilicate glass. In accordance with the NEPA (National Environmental Policy Act) process, an Environmental Impact Statement was prepared for the facility, as well as an Environmental Assessment of the alternative waste forms, and issuance of a Record of Decision (in ...

1991-01-01

72

DWPF waste form compliance plan (Draft Revision)  

Energy Technology Data Exchange (ETDEWEB)

The Department of Energy currently has over 100 million liters of high-level radioactive waste in storage at the Savannah River Site (SRS). In the late 1970`s, the Department of Energy recognized that there were significant safety and cost advantages associated with immobilizing the high-level waste in a stable solid form. Several alternative waste forms were evaluated in terms of product quality and reliability of fabrication. This evaluation led to a decision to build the Defense Waste Processing Facility (DWPF) at SRS to convert the easily dispersed liquid waste to borosilicate glass. In accordance with the NEPA (National Environmental Policy Act) process, an Environmental Impact Statement was prepared for the facility, as well as an Environmental Assessment of the alternative waste forms, and issuance of a Record of Decision (in ...

1991-12-31

73

High-level waste tank modifications, installation of mobilization equipment/check out  

Energy Technology Data Exchange (ETDEWEB)

PUREX high-level waste (HLW) is contained at the West Valley Demonstration Project (WVDP) in an underground carbon-steel storage tank. The HLW consists of a precipitated sludge and an alkaline supernate. This report describes the system that the WVDP has developed and implemented to resuspend and wash the HLW sludge from the tank. The report discusses Sludge Mobilization and Wash System (SMWS) equipment design, installation, and testing. The storage tank required modifications to accommodate the SMWS. These modifications are discussed as well.

1992-08-31

74

Oak Ridge National Laboratory Waste Management Plan, fiscal year 1994. Revision 3  

Energy Technology Data Exchange (ETDEWEB)

US Department of Energy (DOE) Order 5820.2A was promulgated in final form on September 26, 1988. The order requires heads of field organizations to prepare and to submit updates on the waste management plans for all operations under their purview according to the format in Chap. 6, {open_quotes}Waste Management Plan Outline.{close_quotes} These plans are to be submitted by the DOE Oak Ridge Operations Office (DOE-ORO) in December of each year and distributed to the DP-12, ES&H-1, and other appropriate DOE Headquarters (DOE-HQ) organizations for review and comment. This document was prepared in response to this requirement for fiscal year (FY) 1994. The Oak Ridge National Laboratory (ORNL) waste management mission is reduction, collection, storage, treatment, and disposal of DOE wastes, generated primarily in pursuit of ORNL missions, in order to protect human health and safety ...

1993-12-01

75

Liquid waste evaporator operating experience  

Energy Technology Data Exchange (ETDEWEB)

Atomic Energy of Canada Limited (AECL) operates the Waste Treatment Centre (WTC) to treat and immobilize some of the low- level radioactive waste (LLRW) streams at the Chalk River Laboratories (CRL). The WTC at treats low- level radioactive liquid waste by removing the contaminants from the wastewater, concentrating them, and immobilizing them. The fundamental design concept for the WTC is to process the waste streams using forced circulation type liquid waste evaporation (LWE), to solidify the concentrates using thin film evaporator and to discharge the purified effluent into the Ottawa River following verification monitoring. The solidified product drums are stored in existing storage facilities in the CRL. The LWE was installed in the WTC to treat the LLRW. After about four (4) years of design, construction and cold commissioning, the active commissioning of ...

2006-07-01

76

Liquid waste evaporator operating experience  

International Nuclear Information System (INIS)

Atomic Energy of Canada Limited (AECL) operates the Waste Treatment Centre (WTC) to treat and immobilize some of the low- level radioactive waste (LLRW) streams at the Chalk River Laboratories (CRL). The WTC at treats low- level radioactive liquid waste by removing the contaminants from the wastewater, concentrating them, and immobilizing them. The fundamental design concept for the WTC is to process the waste streams using forced circulation type liquid waste evaporation (LWE), to solidify the concentrates using thin film evaporator and to discharge the purified effluent into the Ottawa River following verification monitoring. The solidified product drums are stored in existing storage facilities in the CRL. The LWE was installed in the WTC to treat the LLRW. After about four (4) years of design, construction and cold commissioning, the active commissioning of ...

2005-05-08

77

Inventory of Tank Farm equipment stored or abandoned aboveground  

Energy Technology Data Exchange (ETDEWEB)

This document provides an inventory of Tank Farm equipment stored or abandoned aboveground and potentially subject to regulation. This inventory was conducted in part to ensure that Westinghouse Hanford Company (WHC) does not violate dangerous waste laws concerning storage of potentially contaminated equipment/debris that has been in contact with dangerous waste. The report identifies areas inventoried and provides photographs of equipment.

1994-10-12

78

Comprenhensive Program of Engineering and Geologic Surveys for Designing and Constructing Radioactive Waste Storage Facilities in Hard Rock Massifs  

Energy Technology Data Exchange (ETDEWEB)

Geological, geophysical, and engineering-geological research conducted at the 'Yeniseisky' site obtained data on climatic, geomorphologic, geological conditions, structure and properties of composing rock, and conditions of underground water recharge and discharge. These results provide sufficient information to make an estimate of the suitability of locating a radioactive waste (R W) underground isolation facility at the Nizhnekansky granitoid massif

2002-12-27

79

1993 Annual report on waste generation and waste minimization progress as required by DOE Order 5400.1, Hanford Site  

International Nuclear Information System (INIS)

More important than waste generation numbers, the pollution prevention and waste minimization successes achieved at Hanford in 1993 have reduced waste and improved operations at the Site. Just a few of these projects are: A small research nuclear reactor, unused and destined for disposal as low level radioactive waste, was provided to a Texas University for their nuclear research program, avoiding 25 cubic meters of waste and saving $116,000. By changing the slope on a asphalt lot in front of a waste storage pad, run-off rainwater was prevented from becoming mixed low level waste water, preventing 40 cubic meters of waste and saving $750,000. Through more efficient electrostatic paint spraying equipment and a solvent recovery system, a paint shop reduced hazardous waste by 3,500 ...

80

Risk perception on management of nuclear high-level and transuranic waste storage  

Energy Technology Data Exchange (ETDEWEB)

The Department of Energy`s program for disposing of nuclear High-Level Waste (HLW) and transuranic (TRU) waste has been impeded by overwhelming political opposition fueled by public perceptions of actual risk. Analysis of these perceptions shows them to be deeply rooted in images of fear and dread that have been present since the discovery of radioactivity. The development and use of nuclear weapons linked these images to reality and the mishandling of radioactive waste from the nations military weapons facilities has contributed toward creating a state of distrust that cannot be erased quickly or easily. In addition, the analysis indicates that even the highly educated technical community is not well informed on the latest technology involved with nuclear HLW and TRU waste disposal. It is not surprising then, that the general public feels uncomfortable with DOE`s management plans for with nuclear HLW ...

1994-08-15

81

Treatment for dismantled radioactive solid waste from the TRIGA Mark-2 and 3  

Energy Technology Data Exchange (ETDEWEB)

Radioactive wastes are generally classified into 3 type depending on their physical property: liquid, solid and gaseous type. State-of -the art concerning liquid waste treatment has already been published; KAERI/TR-1315/99. Solid wastes classification package and treatment method will be studied to effectively manage them during the practical decommissioning work. All of the spent fuel produced during the operation of the TRIGA Mark-2 and 3 have been transported to the US last year, 1998, according to the spent fuel management strategy set-up by the US government for the non-proliferation of nuclear energy. Solid wastes are mainly all equipment existing inside of the reactors, activated concrete among the bio-shielded concrete, pipes, pimps, resin filter and it's housings, heat-exchangers, liquid waste storage tanks, to radioactive ...

1999-06-01

82

Transuranic waste form characterization and data base. Executive summary  

Energy Technology Data Exchange (ETDEWEB)

The Transuranic Waste Form Characterization and Data Base (Volume 1) provides a wide range of information from which a comprehensive data base can be established and from which standards and criteria can be developed for the present NRC waste management program. Supplementary information on each of the areas discussed in Volume 1 is presented in Appendices A through K (Volumes 2 and 3). The structure of the study (Volume 1) is outlined and appendices of Volumes 2 and 3 correlate with each main section of the report. The Executive Summary reviews the sources, quantities, characteristics and treatment of transuranic wastes in the United States. Due to the variety of potential treatment processes for transuranic wastes, the end products for long-term storage may have corresponding variations in quantities and characteristics.

1980-09-30

83

National waste terminal storage program. Supplementary quality-assurance requirements  

International Nuclear Information System (INIS)

The basic Quality Assurance Program Requirements standard for the National Waste Terminal Storage Program has been developed primarily for nuclear reactors and other fairly well established nuclear facilities. In the case of waste isolation, however, there are many ongoing investigations for which quality assurance practices and requirements have not been well defined. This paper points out these problems which require supplementary requirements. Briefly these are: (1) the language barrier, that is geologists and scientists are not familiar with quality assurance (QA) terminology; (2) earth sciences deal with materials that cannot be characterized as easily as metals or other materials that are reasonably homogeneous; (3) development and control of mathematical models and associated computer programs; (4) research and development.

84

Wastes behavior and environmental impacts, researches and methods; Comportement des dechets et impacts environnementaux, recherches et methodes  

Energy Technology Data Exchange (ETDEWEB)

The wastes management policy takes into account more and more often the environmental impacts mastership. This evolution is particularly appreciable when the wastes directly interact with the environment: storage, utilization for roads construction and so on. In this context the ADEME organized the 8 june 2000 a colloquium to present the new evaluation methods and tools, to describe the regulations and to identify the research programs needed for this environmental policy. Eleven papers are presented. (A.L.B.)

2001-07-01

85

Gamma Radiation Detectors of the TA-55 Waste Line Monitoring System  

Energy Technology Data Exchange (ETDEWEB)

This report covers the gamma detectors, measurement instrumentation, and testing results of a system developed at Los Alamos National Laboratory. This system monitors the process liquid waste streams at the Plutonium Facility (TA-55) for the presence of radioactive contamination. The detectors are at various points on the acid, caustic, and industrial waste lines. Two of the detectors are on the sanitary sewer lines from the facility. A custom interface unit associated with these two detectors furnishes the facility operation center with a notification of the detection of material. All of the detectors furnish measurement information to a central computer system for storage and trending.

1999-06-01

86

Electronic waste management cost: a scenario-based analysis for Greece.  

Science.gov (United States)

Waste electrical and electronic equipment (WEEE) is recognized as a priority waste stream internationally, mostly due to their volume and hazardousness. This paper presents an analysis for the quantification of WEEE management cost for Greece, taking into consideration scenarios for reverse logistics network's development and WEEE volume scenarios. Transportation cost, which represents a major cost element for any reverse logistics network, is modelled with the use of mathematical programming, targeting towards the optimization of locations for the development of required intermediate storage infrastructures. Additionally, overall operational cost and recycling fees are estimated. PMID:21242175

2011-01-17

87

Subcritical Noise Analysis Measurements with Fresh and Spent Research Reactor Fuels Elements  

Energy Technology Data Exchange (ETDEWEB)

The verification of the subcriticality is of utmost importance for the safe transportation and storage of nuclear reactor fuels. Transportation containers and storage facilities are designed such that nuclear fuels remain in a subcritical state. Such designs often involve excess conservatism because of the lack of relevant experimental data to verify the accuracy of Monte Carlo codes used in nuclear criticality safety analyses. A joint experimental research program between Oak Ridge National Laboratory, Westinghouse Safety Management Solutions, Inc., and the University of Missouri was initiated to obtain measured quantities that could be directly related to the subcriticality of simple arrays of Missouri University Research Reactor (MURR) fuel elements. A series of measurement were performed to assess the reactivity of materials such as BORAL, stainless steel, aluminum, and lead that are typically used in the construction of shipping ...

1999-02-01

88

Uranium-233 waste definition: Disposal options, safeguards, criticality control, and arms control  

Energy Technology Data Exchange (ETDEWEB)

The US investigated the use of {sup 233}U for weapons, reactors, and other purposes from the 1950s into the 1970s. Based on the results of these investigations, it was decided not to use {sup 233}U on a large scale. Most of the {sup 233}U-containing materials were placed in long-term storage. At the end of the cold war, the US initiated, as part of its arms control policies, a disposition program for excess fissile materials. Other programs were accelerated for disposal of radioactive wastes placed in storage during the cold war. Last, potential safety issues were identified related to the storage of some {sup 233}U-containing materials. Because of these changes, significant activities associated with {sup 233}U-containing materials are expected. This report is one of a series of reports to provide the technical bases for future decisions on how to manage this material. A basis for defining when {sup ...

1998-07-07

89

Strategic principles workshops: Discussion drafts and workshop notes  

Energy Technology Data Exchange (ETDEWEB)

The Office of Civilian Radioactive Waste-Management in the Department of Energy (DOE) is responsible for disposing of this nation`s spent fuel and high-level radioactive waste in a manner that protects the health and safety of the public and the quality of the environment. Although embodied in the Federal repository program that began with studies in the late 1950s, this mission was explicitly established by the Nuclear Waste Policy Act of 1982 and reaffirmed by the Nuclear Waste Policy Amendments Act of 1987. To fulfill our mission, we are developing a waste management system consisting of a geologic repository for permanent disposal deep beneath the surface of the earth, a facility for monitored retrievable storage, and a system for transporting the waste. This discussion draft was developed to help involve parties affected by or ...

1991-09-01

90

The Development on Evaluation Response Spectrum for the Seismic Risk Evaluation of a Nuclear Waste Repository  

Energy Technology Data Exchange (ETDEWEB)

Long-term disposal and management of low and intermediate-level radioactive waste is a major project of the nuclear power industry. Therefore, the selection of an underground waste repository has to be a geologically and seismologically stable storage. Easy transportation and emplacement is essential. The Wolsung nuclear power plant (NPP) of unit no. 1/2/ 3/ 4, which is responsible for the future of the energy industry, has already been constructed at the Wolsung site and a New NPP has recently been created at the Sinwolsung site. Radioactive waste used in the plant facilities, has piled up increasingly every year, but it should be taken to be managed at long-term underground storage disposal facilities. The Wolsung site for radioactivity waste repository was known to be relatively stable through various geological surveys, earthquakes, groundwater, engineering ...

2010-05-15

91

The Development on Evaluation Response Spectrum for the Seismic Risk Evaluation of a Nuclear Waste Repository  

International Nuclear Information System (INIS)

Long-term disposal and management of low and intermediate-level radioactive waste is a major project of the nuclear power industry. Therefore, the selection of an underground waste repository has to be a geologically and seismologically stable storage. Easy transportation and emplacement is essential. The Wolsung nuclear power plant (NPP) of unit no. 1/2/ 3/ 4, which is responsible for the future of the energy industry, has already been constructed at the Wolsung site and a New NPP has recently been created at the Sinwolsung site. Radioactive waste used in the plant facilities, has piled up increasingly every year, but it should be taken to be managed at long-term underground storage disposal facilities. The Wolsung site for radioactivity waste repository was known to be relatively stable through various geological surveys, earthquakes, groundwater, engineering ...

2010-05-01

92

B Plant treatment, storage, and disposal (TSD) units inspection plan  

Energy Technology Data Exchange (ETDEWEB)

This inspection plan is written to meet the requirements of WAC 173-303 for operations of a TSD facility. Owners/operators of TSD facilities are required to inspection their facility and active waste management units to prevent and/or detect malfunctions, discharges and other conditions potentially hazardous to human health and the environment. A written plan detailing these inspection efforts must be maintained at the facility in accordance with Washington Administrative Code (WAC), Chapter 173-303, ``Dangerous Waste Regulations`` (WAC 173-303), a written inspection plan is required for the operation of a treatment, storage and disposal (TSD) facility and individual TSD units. B Plant is a permitted TSD facility currently operating under interim status with an approved Part A Permit. Various operational systems and locations within or under the control of B Plant have been permitted for waste ...

1996-04-26

93

The review of radioactive waste management in the world  

International Nuclear Information System (INIS)

Radioactive waste is generally classified on the basis of how much radiation and the type of radiation it emits as well as the length of time over which it will continue to emit radiation. Many activities dealing with radioactive materials produce nuclear wastes, including civilian nuclear power programs (nuclear Power plant operations and nuclear fuel-cycle activities), defense nuclear programs (nuclear weapons production, naval nuclear reactor programs, and related R and D), and industrial and institutional activities (scientific research, medical operations, and other industrial uses of Radioisotopic sources or Radio chemicals). To minimize the potential adverse health and environment impacts to people and other systems including of animals, plant and etc, during the entire lifetime of the radionuclides involved, nuclear waste must be carefully and properly managed. The scope of nuclear - waste ...

94

Resource Conservation and Recovery Act, Part B permit application [for the Waste Isolation Pilot Plant (WIPP)]. Volume 4, Revision 1.0  

Energy Technology Data Exchange (ETDEWEB)

The US Department of Energy is currently constructing the Waste Isolation Pilot near Carlsbad, New Mexico. The full-scale pilot plant will demonstrate the feasibility of the safe disposal of defense-related nuclear waste in a bedded salt formation at a depth of 2160 feet below the surface. WIPP will provide for the permanent storage of 25,000 cu ft of remote-handled (RH) transuranic waste and 6,000,000 cu ft of contact-handled (CH) transuranic waste. This paper covers the major mechanical/structural design considerations for the waste hoist and its hoist tower structure. The design of the hoist system and safety features incorporates state-of-the-art technology developed in the hoist and mining industry to ensure safe operation for transporting nuclear waste underground. Also included are design specifications for VOC-10 monitoring system.

1991-12-31

95

Actinides in liquid waste formed in the regeneration of nuclear fuel from a VVER-1000 reactor  

International Nuclear Information System (INIS)

In the radiochemical reprocessing of spent fuel from nuclear reactors, a considerable amount of liquid, solid, and gaseous waste is formed; this waste is potentially dangerous to humans and requires the development of special and complex technological techniques for its localization and reliable long-term storage. The most hazardous are liquid wastes of high specific activity - water-tailings solutions obtained in the first cycle of extraction after the removal of uranium and plutonium. These solutions contain more than 99.9% of all the other transuranic elements - isotopes of neptunium, americium, and curium. Where necessary, some fission products and actinides may be removed from wastes of high specific activity for subsequent use. The quantity, composition, and activity of these wastes varies within broad limits, depending on the type and power of the ...

96

Safety analysis report: packages. Pu oxide and Am oxide shipping cask (Packaging of fissile and other radioactive materials. Final report  

Energy Technology Data Exchange (ETDEWEB)

The PuO/sub 2/ cask or SP 5320-2 and 3 cask is designed for surface shipment of americium or plutonium. The cask design was physically tested to demonstrate that it met the criteria specified in US ERDA Manual Chapter 0529, and Chapter I, Interstate Commerce Commission. The package has been assessed for transport of up to 357 grams of plutonium (403 grams PuO/sub 2/ powder) and up to 176 grams of americium (200 grams AmO/sub 2/ powder), having a maximum decay heat of 203 watts. Criticality evaluation alone would allow the shipment as Fissile Class II but the radiation level of the cask, measured at the time of shipment, may exceed 50 mrem/h at the surface and require shipment as Fissile Class III. Sample calculations address only the more restrictive of the two materials, which in most cases is /sup 238/PuO/sub 2/.

1980-05-01

97

Nuclear wastes management: the lessons from the C.S.M. disposal site (Centre de Stockage de la Manche). Memory-less Centre, Future-less Centre?; Gestion des dechets radioactifs: les lecons du Centre de Stockage de la Manche (C.S.M.). Centre Sans Memoire, Centre Sans Avenir?  

Energy Technology Data Exchange (ETDEWEB)

With its 527 217 m{sup 3} of low and medium activity wastes put in storage between 1969 and 1994, the C.S.M.( center of storage of Manche) is and remains to this day a necessary element to understand the problems posed by the eternal storage of nuclear materials and the limits of the notion of reversibility. There are therefore teachings to be drawn. We cannot repeat past mistakes in particular with high activity wastes which we wish to bury deep underground. This report is based on the analysis of the existing bibliography, of the internal A.N.D.R.A. documents which we released to the public, of the lessons drawn from our participation in the official concerting and work groups, and finally of the data obtained after inquiries were done in the region in the framework of R.I.V.I.E;R.E. (citizens network of radioecological surveillance, information and evaluation). In spite of all ...

2006-05-15

98

Thermal Modeling and Performance Analysis of Interim Dry Storage and Geologic Disposal Facilities for Spent Nuclear Fuel  

Science.gov (United States)

Thermal models are constructed and analyses are performed of aluminum-based spent nuclear fuel (Al-SNF) in interim dry storage and geologic disposal configurations. Two models are developed, referred to as the interim storage model and the codisposal waste package (WP) model. Time-dependent source terms of Al-SNF forms and the defense high-level waste (DHLW) canisters are also developed for thermal performance analysis of the geologic codisposal WP.The interim storage model is a three-dimensional conduction-convection conjugate model to investigate the natural convection cooling of a sealed dry storage canister with vertical orientation in a dry storage vault. The analysis is made for various decay heat sources (equivalent to 25 to 35 kW/m{sup 3}) using various boundary conditions around the canister wall and with backfilled nitrogen or ...

2000-07-15

99

Structural acceptance criteria for the evaulation of existing double-shell waste storage tanks located at the Hanford site, Richland, Washington  

Energy Technology Data Exchange (ETDEWEB)

The structural acceptance criteria contained herein for the evaluation of existing underground double-shell waste storage tanks located at the Hanford Site is part of the Life Management/Aging Management Program of the Tank Waste Remediation System. The purpose of the overall life management program is to ensure that confinement of the waste is maintained over the required service life of the tanks. Characterization of the present condition of the tanks, understanding and characterization of potential degradation mechanisms, and development of tank structural acceptance criteria based on previous service and projected use are prerequisites to assessing tank integrity, to projecting the length of tank service, and to developing and applying prudent fixes or repairs. The criteria provided herein summarize the requirements for the analysis and structural qualification of the existing double-shell tanks for ...

1995-09-01

100

Evaluation of the concept SPEOS applied to the exploitation of industrial waste heat stored in an underground seasonal storage; Prospection et evaluation du potentiel d`application du concept SPEOS a la valorisation des rejets thermiques industriels par stockage saisonnier souterrain  

Energy Technology Data Exchange (ETDEWEB)

SPEOS takes advantage of a geological situation which apparently does not occur much in Switzerland. The SPEOS pilot installation, which was erected in 1982, is designed for the supply of heat for about 500 persons. In the course of 10 cycles, the possibilities and limits of the seasonal heat storage were displayed. It was demonstrated that large quantities of heat with temperatures of up to 75 C can be stored in an aquifer. The behaviour of such a storage can be predicted with sufficient accuracy with mathematical models. (author) 12 refs.

1993-09-01

101

Energy storage for hybrid remote power systems  

Energy Technology Data Exchange (ETDEWEB)

Energy storage can be a cost-effective component of hybrid remote power systems. Storage serves the special role of taking advantage of intermittent renewable power sources. Traditionally this role has been played by lead-acid batteries, which have high life-cycle costs and pose special disposal problems. Hydrogen or zinc-air storage technologies can reduce life-cycle costs and environmental impacts. Using projected data for advanced energy storage technologies, LLNL ran an optimization for a hypothetical Arctic community with a reasonable wind resource (average wind speed 8 m/s). These simulations showed the life-cycle annualized cost of the total energy system (electric plus space heating) might be reduced by nearly 40% simply by adding wind power to the diesel system. An additional 20 to 40% of the wind-diesel cost might be saved by adding hydrogen storage or zinc-air fuel cells ...

1998-03-01

102

The high level and long lived radioactive wastes; Les dechets radioactifs a haute activite et a vie longue  

Energy Technology Data Exchange (ETDEWEB)

This report presents the main conclusions of 15 years of researches managed by the CEA. This report is the preliminary version of the 2005 final report. It presents the main conclusions of the actions on the axis 1 and 3 of the law of the 30 December 1991. The synthesis report on the axis 1 concerns results obtained on the long lived radionuclides separation and transmutation in high level and long lived radioactive wastes. the synthesis report on the axis 3 presents results obtained by the processes of conditioning and of ground and underground long term storage. (A.L.B.)

2005-07-01

103

Development of advanced electrochemical emission spectroscopy for monitoring corrosion in simulated DOE liquid waste. 1998 annual progress report  

Energy Technology Data Exchange (ETDEWEB)

'Objective of this project is to develop and use Electrochemical Emission Spectroscopy (EES) and other electrochemical techniques as in situ tools for exploring corrosion mechanisms of iron and carbon steel in highly alkaline solutions and for continuously monitoring corrosion on structural materials in DOE liquid waste storage system. In particular, the author will explore the fundamental aspects of the passive behavior of pure iron since breakdown of passivity leads to localized corrosion. This report summarizes work after 1 year of a 3 year project.'

1998-06-01

104

Chemical compatibility study of Cooley L18KU, Herculite, and Elephant Mat with Hanford tank waste  

Energy Technology Data Exchange (ETDEWEB)

An independent chemical compatibility review of various wrapping and absorbent/padding materials was conducted to evaluate resistance to chemicals and constituents present in liquid waste from the Hanford underground tanks. These materials will be used to wrap long-length contaminated equipment when such equipment is removed from the tanks and prepared for transportation and subsequent disposal or storage. The materials studied were Cooley L18KU, Herculite, and Elephant Mat. The study concludes that these materials are appropriate for use in this application.

1998-06-23

105

Maintenance Implementation Plan for solid waste  

Energy Technology Data Exchange (ETDEWEB)

This Maintenance Implementation Plan (MIP) has been developed for. implementation of the US Department of Energy (DOE) Order 4330.4A. Maintenance Implementation Program (DOE 1990) at the Hanford Site Solid Waste complex. It addresses maintenance functions associated with Solid Waste Management, which includes the field operational group and the facilities operational group. An assessment of the existing maintenance programs for Solid Waste was performed, and the results of this assessment were evaluated to determine corrective actions required to bring Solid Waste Maintenance into compliance with the order. The MIP assessment disclosed that most elements defined in the order are currently implemented for Solid Waste. It also identified issues which must be addressed to bring the maintenance function into full compliance with DOE Order 4330.4A. These include documentation of the ...

1992-06-01

106

Laboratory for characterization of spent nuclear fuel and high/medium level radioactive waste. Experimental results and performances  

International Nuclear Information System (INIS)

During the phases of separation, treatment, conditioning and storage of radioactive waste, destructive and nondestructive methods for their characterization are needed. In order to satisfy this necessity, in the frame of the National Program of Research and Development, the 'Laboratory for characterization of spent nuclear fuel and high/medium level radioactive waste- LABORAD' was created. The purpose of the project was to accredit the analysis methods available in the laboratory, and also to develop new methods for the characterization of the radioactive waste. A special attention was paid to the high-level radioactive waste and spent nuclear fuel characterization that require special facilities for handling. These facilities (e.g. hot cells, remote handlers, transport container) are already available in our institute. Experimental results and performances obtained during ...

2009-05-27

107

Control of the reduction/oxidation potential of Hanford Waste Vitrification Plant feeds  

International Nuclear Information System (INIS)

A schematic diagram shows the various processing steps to be performed during feed preparation in the Hanford Waste Vitrification Plant (HWVP). The pretreated NCAW is transferred to the slurry receipt adjustment tank (SRAT) in the HWVP for concentration. Water removed during boildown is collected in the slurry mix evaporator condensate tank (SMECT). After waste treatment the water is returned to the storage tanks for eventual disposal. The pretreated Neutralized Current Acid Waste (NCAW) is concentrated in the SRAT to approximately 125 g waste oxides/ liter. Formic acid is then added at a controlled rate to improve rheological properties and achieve a required reduction/oxidation state. Reflux boiling is initiated and continued for several hours. The concentrated slurry is cooled and pumped to the slurry mix evaporator (SME). In the SME, glass frit is added, and the slurry is ...

1988-09-11

108

Characterization system for Germanium detectors dedicated to gamma spectroscopy applied to nuclear waste  

International Nuclear Information System (INIS)

CEA-Valduc produces some radioactive waste (mainly alpha emitters). Legislation requires producers to sort their waste by activity and type of isotopes, and to package them in order to forward them to the appropriate reprocessing or storage facility. Our lab LMDE (laboratory for measurements on nuclear wastes and valuation) is in charge of the characterization of the majority of waste produced by CEA-Valduc. Among non-destructive methods to characterize a radioactive object, gamma-spectroscopy is one of the most efficient. We present to this conference the method we use to characterize nuclear waste and the system we developed to characterize our germanium detectors. The goal of this system is to obtain reliable numerical models of our detectors and calculate their efficiency curves. Measurements are necessary to checks models and improve them. These ...

2009-06-07

109

A PC-based software package for modeling DOE mixed-waste management options  

Energy Technology Data Exchange (ETDEWEB)

The U.S. Department of Energy (DOE) Headquarters and associated contractors have developed an IBM PC-based software package that estimates costs, schedules, and public and occupational health risks for a range of mixed-waste management options. A key application of the software package is the comparison of various waste-treatment options documented in the draft Site Treatment Plans prepared in accordance with the requirements of the Federal Facility Compliance Act of 1992. This automated Systems Analysis Methodology consists of a user interface for configuring complexwide or site-specific waste-management options; calculational algorithms for cost, schedule and risk; and user-selected graphical or tabular output of results. The mixed-waste management activities modeled in the automated Systems Analysis Methodology include waste storage, characterization, ...

1995-02-01

110

Waste Minimization/Pollution Prevention Crosscut Plan, 1994  

International Nuclear Information System (INIS)

This plan establishes a Department-wide goal to reduce total releases of toxic chemicals to the environment and off-site transfers of such toxic chemicals by 50 percent by December 31, 1999, in compliance with Executive Order 12856. Each site that meets the threshold quantities of toxic chemicals established in the Emergency Planning and Community Right-to-Know Act (EPCRA) will participate in this goal. In addition, each DOE site will establish site-specific goals to reduce generation of hazardous, radioactive, radioactive mixed, and sanitary wastes and pollutants, as applicable. Implementation of this plan will represent a major step toward the environmental risks and costs associated with DOE operations and increasing the Department's use of preventive environmental management practices. Investing in Waste Minimization Pollution Prevention (WMin/PP) steadily reduce hazardous and radioactive waste generation and will ...

111

Corrosion studies of carbon steel under impinging jets of simulated slurries of neutralized current acid waste (NCAW) and neutralized cladding removal waste (NCRW)  

Energy Technology Data Exchange (ETDEWEB)

Plans for the disposal of radioactive liquid and solid wastes presently stored in double-shell tanks at the Hanford Site call for retrieval and processing of the waste to create forms suitable for permanent disposal. Waste will be retrieved from a tank using a submerged slurry pump in conjunction with one or more rotating slurry jet mixer pumps. Pacific Northwest Laboratory (PNL) has conducted tests using simulated waste slurries to assess the effects of a impinging slurry jet on the corrosion rate of the tank wall and floor, an action that could potentially compromise the tank's structural integrity. Corrosion processes were investigated on a laboratory scale with a simulated neutralized cladding removal waste (NCRW) slurry and in a subsequent test with simulated neutralized current acid waste (NCAW) slurry. The test slurries simulated the actual NCRW ...

1992-01-01

112

Corrosion studies of carbon steel under impinging jets of simulated slurries of neutralized current acid waste (NCAW) and neutralized cladding removal waste (NCRW)  

Energy Technology Data Exchange (ETDEWEB)

Plans for the disposal of radioactive liquid and solid wastes presently stored in double-shell tanks at the Hanford Site call for retrieval and processing of the waste to create forms suitable for permanent disposal. Waste will be retrieved from a tank using a submerged slurry pump in conjunction with one or more rotating slurry jet mixer pumps. Pacific Northwest Laboratory (PNL) has conducted tests using simulated waste slurries to assess the effects of a impinging slurry jet on the corrosion rate of the tank wall and floor, an action that could potentially compromise the tank`s structural integrity. Corrosion processes were investigated on a laboratory scale with a simulated neutralized cladding removal waste (NCRW) slurry and in a subsequent test with simulated neutralized current acid waste (NCAW) slurry. The test slurries simulated the actual NCRW and NCAW ...

1992-01-01

113

Long-term storage facility for reactor compartments in Sayda Bay - German support for utilization of nuclear submarines in Russia  

Science.gov (United States)

The German-Russian project that is part of the G8 initiative on Global Partnership Against the Spread of Weapons and Materials of Mass Destruction focuses on the speedy construction of a land-based interim storage facility for nuclear submarine reactor compartments at Sayda Bay near Murmansk. This project includes the required infrastructure facilities for long-term storage of about 150 reactor compartments for a period of about 70 years. The interim storage facility is a precondition for effective activities of decommissioning and dismantlement of almost all nuclear-powered submarines of the Russian Northern Fleet. The project also includes the establishment of a computer-assisted waste monitoring system. In addition, the project involves clearing Sayda Bay of other shipwrecks of the Russian navy. On the German side the project is carried out by the Energiewerke Nord GmbH (EWN) on behalf of the Federal ...

2007-07-01

114

2007 SB14 Source Reduction Plan/Report  

Energy Technology Data Exchange (ETDEWEB)

Aqueous solutions (mixed waste) generated from various LLNL operations, such as debris washing, sample preparation and analysis, and equipment maintenance and cleanout, were combined for storage in the B695 tank farm. Prior to combination the individual waste streams had different codes depending on the particular generating process and waste characteristics. The largest streams were CWC 132, 791, 134, 792. Several smaller waste streams were also included. This combined waste stream was treated at LLNL's waste treatment facility using a vacuum filtration and cool vapor evaporation process in preparation for discharge to sanitary sewer. Prior to discharge, the treated waste stream was sampled and the results were reviewed by LLNL's water monitoring specialists. The treated solution was discharged ...

2007-07-24

115

Nuclear cask testing films misleading and misused  

Energy Technology Data Exchange (ETDEWEB)

In 1977 and 1978, Sandia National Laboratories, located in Albuquerque, New Mexico, and operated for the US Department of Energy (DOE), filmed a series of crash and fire tests performed on three casks designed to transport irradiated nuclear fuel assemblies. While the tests were performed to assess the applicability of scale and computer modeling techniques to actual accidents, films of them were quickly pressed into service by the DOE and nuclear utilities as ``proof`` to the public of the safety of the casks. In the public debate over the safety of irradiated nuclear fuel transportation, the films have served as the mainstay for the nuclear industry. Although the scripts of all the films were reviewed by USDOE officials before production, they contain numerous misleading concepts and images, and omit significant facts. The shorter versions eliminated qualifying statements contained in the longer version, and created false impressions. This ...

1991-10-01

116

Key Performance Criteria Affecting the Most the Safety of a Nuclear Waste Long Term Storage : A Case Study Commissioned by CEA  

Energy Technology Data Exchange (ETDEWEB)

As part of the work scope set in the French law on high level long lived waste R&D passed in 1991, CEA is conducting a research program to establish the scientific basis and assess the feasibility of long term storage as an option for the safe management of nuclear waste for periods as long as centuries. This goal is a significant departure from the current industrial practice where storage facilities are usually built to last only a few decades. From a technical viewpoint such an extension in time seems feasible provided care and maintenance is exercised. Considering such long periods of time, the risk for Society of loosing oversight and control of such a facility is real, which triggers the question of whether and how long term storage safety can be actually achieved. Therefore CEA commissioned a study (1) in which MUTADIS Consultants (2) and CEPN (3) were both involved. ...

2003-02-24

117

Waste Receiving and Processing Facility Module 2A: Advanced Conceptual Design Report. Volume 1  

Energy Technology Data Exchange (ETDEWEB)

This ACDR was performed following completed of the Conceptual Design Report in July 1992; the work encompassed August 1992 to January 1994. Mission of the WRAP Module 2A facility is to receive, process, package, certify, and ship for permanent burial at the Hanford site disposal facilities the Category 1 and 3 contact handled low-level radioactive mixed wastes that are currently in retrievable storage at Hanford and are forecast to be generated over the next 30 years by Hanford, and waste to be shipped to Hanford from about DOE sites. This volume provides an introduction to the ACDR process and the scope of the task along with a project summary of the facility, treatment technologies, cost, and schedule. Major areas of departure from the CDR are highlighted. Descriptions of the facility layout and operations are included.

1994-03-01

118

Uncertainty analysis for low-level radioactive waste disposal performance assessment at Oak Ridge National Laboratory  

Energy Technology Data Exchange (ETDEWEB)

A performance assessment of the operating Solid Waste Storage Area 6 (SWSA 6) facility for the disposal of low-level radioactive waste at the Oak Ridge National Laboratory has been prepared to provide the technical basis for demonstrating compliance with the performance objectives of DOE Order 5820.2A, Chapter 111.2 An analysis of the uncertainty incorporated into the assessment was performed which addressed the quantitative uncertainty in the data used by the models, the subjective uncertainty associated with the models used for assessing performance of the disposal facility and site, and the uncertainty in the models used for estimating dose and human exposure. The results of the uncertainty analysis were used to interpret results and to formulate conclusions about the performance assessment. This paper discusses the approach taken in analyzing the uncertainty in the performance assessment and the role of uncertainty in ...

1994-12-31

119

Transmutation of nuclear waste. Transmutatie van kernafval; Statusrapport programma Recyclage van Actiniden en Splijtingsprodukten (RAS)  

Energy Technology Data Exchange (ETDEWEB)

The most important aim of the title program is to investigate the possibility to convert long-lived actinides and mobile fission products in short-lived and stable isotopes by means of nuclear transmutation and recycling. First, an overview is given of the present situation regarding fission material waste, the origin of such waste in light water reactors and the options for interim and ultimate storage. Next, attention is paid to the aim of the the RAS program, the working method and the results so far of national and international research on the transmutation of actinides and fission products. Speculative expectations for the future are briefly outlined. The report also contains four appendices with technical aspects of the title subject: the RAS program of ECN, chemical aspects of reprocessing fission material, transmutation in fission reactors and in accelerators. 12 figs., 7 tabs., 4 appendices, 57 refs.

1993-07-01

120

home  

Wastenet

... It has 2x 15L bins: one for food waste, the other for recycling, which slide out on ball bearing steel runners. Both have plastic inner buckets that can be lifted out. Supplied with fixing brackets. To fit 30cm-wide cabinets Filed Under: Top Products Tagged With: bedroom, bins, drawers, drawersshelveskitchenbins, garden, home, homegardenbedroomstorage, John Lewis, kitchen, shelves, storage ...

121

What's the rest of the world doing with its spent nuclear fuel?  

International Nuclear Information System (INIS)

This paper discusses the storage of spent nuclear fuel by countries around the world. At the present time, all countries are storing it. A small number of countries are reprocessing it for recycling. Essentially all countries are preparing for eventual disposal of end waste form. There is much uncertainty and controversy over what should and will happen.

2008-06-01

122

The European volcanic ash crisis: Between international and European law | EurActiv  

Wastenet

... Carbon capture and storage Waste Prevention and Recycling EU clean air strategy Environmental liability: Applying the 'polluter pays' principle What goes around ...comes around: Recycling and climate change Behind closed doors: Air quality in buildings Keeping cool with refrigerants: The F-gas review Regions fighting climate ...

123

ORNL `90  

Energy Technology Data Exchange (ETDEWEB)

This overview of research conducted at ORNL in 1991 presents information on the subjects of biology, physics, and the environment. Specific topics include gene mutations in kidney disease, technology assessments in thermonuclear fusion, submarine hunting technology, ozone-safe refrigerants, optical data storage via surface enhanced raman spectroscopy, and waste mitigating microbes. (GHH)

1990-12-31

124

ORNL '90  

Energy Technology Data Exchange (ETDEWEB)

This overview of research conducted at ORNL in 1991 presents information on the subjects of biology, physics, and the environment. Specific topics include gene mutations in kidney disease, technology assessments in thermonuclear fusion, submarine hunting technology, ozone-safe refrigerants, optical data storage via surface enhanced raman spectroscopy, and waste mitigating microbes. (GHH)

1990-01-01

125

Institutional models for nuclear fuel cycle facilities  

International Nuclear Information System (INIS)

The possibility of having properly designed multinational fuel cycle agreements which would contribute to public acceptance of nuclear energy are explored. The advantages of existing international cooperation in the field of uranium enrichment and nuclear waste disposal and reprocessing are discussed. The possible forms of multinational co-operation under an international organisation, committed the non-proliferation and operating under international law and covering storage facilities, security of raw materials and the nuclear fuel cycle are summarised in model form. (U.K.).

126

High level waste storage tanks 242-A evaporator S/RID phase II assessment report  

Energy Technology Data Exchange (ETDEWEB)

This document, the Standards/Requirements Identification Document (S/RID) Phase 2 Assessment Report for the subject facility, represents the results of a Performance Assessment to determine whether procedures containing S/RID requirements are fully implemented by field personnel in the field. It contains a summary report and three attachments; an assessment schedule, performance objectives, and assessments for selected functional areas.

1996-09-27

127

High level waste storage tank farms/242-A evaporator standards/requirements identification document phase 1 assessment report  

Energy Technology Data Exchange (ETDEWEB)

This document, the Standards/Requirements Identification Document (S/RID) Phase I Assessment Report for the subject facility, represents the results of an Administrative Assessment to determine whether S/RID requirements are fully addressed by existing policies, plans or procedures. It contains; compliance status, remedial actions, and an implementing manuals report linking S/RID elements to requirement source to implementing manual and section.

1996-09-30

128

An approach to software quality assurance for robotic inspection systems  

International Nuclear Information System (INIS)

Software quality assurance (SQA) for robotic systems used in nuclear waste applications is vital to ensure that the systems operate safely and reliably and pose a minimum risk to humans and the environment. This paper describes the SQA approach for the control and data acquisition system for a robotic system being developed for remote surveillance and inspection of underground storage tanks (UST) at the Hanford Site.

1993-11-14

129

Low-activity waste envelope definitions for the TWRS Privatization Phase I Request For Proposal  

Energy Technology Data Exchange (ETDEWEB)

Radioactive waste has been stored in large underground storage tanks at the Hanford Site since 1944. Approximately 212 million liters of waste containing approximately 240,000 metric tons of processed chemicals and 177 mega-curies of radionuclides are now stored in 177 tanks. These caustic wastes are in the form of liquids, slurries, saltcakes, and sludge. In 1991, the Tank Waste Remediation System (TWRS) Program was established to manage, retrieve, treat, immobilize, and dispose of these wastes in a safe, environmentally sound, and cost-effective manner. The Department of Energy (DOE) has believes that it is feasible to privatize portions of the TWRS Program. Under the privatization strategy embodied in the Request for Proposal (RFP), DOE will purchase services from a contractor-owned, contractor-operated facility under a fixed-price contract. Phase I of the ...

1996-11-01

130

Bitumen immobilization of aqueous radwaste by thin-film evaporation  

International Nuclear Information System (INIS)

In the early 1980s, AECL built a Waste Treatment Centre (WTC) for managing low-level solid and aqueous liquid wastes for converting CANDU wastes. At present, two liquid waste streams are being treated at the WTC. The liquid waste streams are volume-reduced by a combination of continuous crossflow microfiltration (MF), spiral wound reverse osmosis (SWRO) and tubular reverse osmosis (TRO) membrane technologies. The concentrate produced from the TRO system and the volume-reduced MF backwash solutions are evaporated while simultaneously adding bitumen in a thin-film evaporator. A water-free product of chemical and radiochemical salts and bitumen is removed in 200-L galvanized steel drums for storage. The radiation field of product drums on contact typically has a value of 0.5 to 3 R/h depending upon the feed concentration of radioactivity to the evaporator. The ...

1996-02-25

131

Assessing waste management systems using reginalt software  

Energy Technology Data Exchange (ETDEWEB)

A method for assessing management systems for low-level radioactive waste is being developed for US Department of Energy. The method is based on benefit-cost-risk analysis. Waste management is broken down into its component steps, which are generation, treatment, packaging, storage, transportation, and disposal. Several different alternatives available for each waste management step are described. A particular waste management system consists of a feasible combination of alternatives for each step. Selecting an optimal waste management system would generally proceed as follows: (1) qualitative considerations are used to narrow down the choice of waste management system alternatives to a manageable number; (2) the costs and risks for each of these system alternatives are evaluated; (3) the number of alternatives is further reduced by ...

1988-03-01

132

Numerical analysis of a natural convection cooling system for radioactive canisters storage  

International Nuclear Information System (INIS)

This paper describes the use of numerical analysis for studying natural convection cooling systems for long term storage of heat producing radioactive materials, including special nuclear materials and nuclear waste. The paper explains the major design philosophy, and shares the experiences of numerical modeling. The strategy of storing radioactive material is to immobilize nuclear high-level waste by a vitrification process, convertion it into borosilicate glass, and cast the glass into stainless steel canisters. These canisters are seal welded, decontaminated, inspected, and temporarily stored in an underground vault until they can be sent to a geologic repository for permanent storage. These canisters generate heat by nuclear decay of radioactive isotopes. The function of the storage facility ventilation system is to ensure that the glass centerline temperature does not exceed ...

1995-02-01

133

Quality assurance requirements and description for the Civilian Radioactive Waste Management Program  

International Nuclear Information System (INIS)

The Quality Assurance Requirements and Description (QARD) is the principal quality assurance document for the Civilian Radioactive Waste Management Program (Program). It establishes the minimum requirements for the Quality Assurance Program. The QARD contains regulatory requirements and program commitments necessary for the development of an effective quality assurance program. Quality assurance implementing documents must be based on, and consistent with, QARD requirements. The QARD applies to the following: (1) acceptance of spent nuclear fuel and high-level radioactive waste; (2) transport of spent nuclear fuel and high-level radioactive waste; (3) the Monitored Retrievable Storage (MRS) facility through application for an operating license; (4) Mined Geologic Disposal System (MGDS), including the site characterization activities (exploratory studies facility (ESF) and surface based testing), through ...

134

Ion exchange at TNX using the SKID unit  

Energy Technology Data Exchange (ETDEWEB)

An ion exchange unit has been manufactured for WSRC by British Nuclear Fuels, Ltd. This unit consists of three columns, ancillary valving, pumps, lines, and computer controls. It has been delivered to TNX for use in testing a cesium-specific ion exchange resin, developed at WSRC as a potential second generation process for the decontamination of Defense Waste Processing Facility (DWPF) supernate. This resin also has Department of Energy applications at both Oak Ridge and Hanford. Oak Ridge is interested in decontaminating the Melton Valley storage tank supernate, while Hanford is interested in decontaminating the 101-AW and 101-SY supernate streams. Another potential developmental interest is the Savannah River Site (SRS) DWPF recycle stream. The three primary waste streams of interest are the Oak Ridge, Hanford, and SRS, SWPF supernate streams. For these three waste streams, the cesium decontamination ...

1993-10-21

135

Hanford facility dangerous waste permit application, general information portion  

Energy Technology Data Exchange (ETDEWEB)

The `Hanford Facility Dangerous Waste Permit Application` is considered to be a single application organized into a General Information Portion (this document, DOE/RL-91-28) and a Unit- Specific Portion. The scope of the General Information Portion includes information that could be used to discuss operating units, units undergoing closure, or units being dispositioned through other options. Documentation included in the General Information Portion is broader in nature and could be used by multiple treatment, storage, and/or disposal units. A checklist indicating where information is contained in the General Information Portion, in relation to the Washington State Department of Ecology guidance documentation, is located in the Contents Section. The intent of the General Information Portion is: (1) to provide an overview of the Hanford Facility; and (2) to assist in streamlining efforts associated with treatment, storage, ...

1996-07-29

136

The Performance of Spent Fuel Casks in Severe Tunnel Fires  

International Nuclear Information System (INIS)

The Nuclear Regulatory Commission (NRC), working with the National Institute of Standards and Technology (NIST), Pacific Northwest National Laboratory (PNNL), and the National Transportation Safety Board (NTSB), performed analyses to predict the response of various spent fuel transportation cask designs when exposed to a fire similar to that which occurred in the Howard Street railroad tunnel in downtown Baltimore, Maryland on July 18, 2001. The thermal performance of three different spent fuel cask designs (HOLTEC HI-STAR 100, TransNuclear TN-68, and NAC-LWT) was evaluated with the ANSYSR and COBRA-SFS analysis codes, utilizing boundary conditions for the tunnel fire obtained using NIST's Fire Dynamics Simulator (FDS) code. NRC Staff evaluated the potential for a release of radioactive material from each of the three transportation casks analyzed for the Baltimore tunnel fire scenario. The results of these analyses are ...

2005-11-01

137

Shielding and Criticality Safety Analysis of KSC-1 Cask for the High Burnup PWR Spent Fuels  

International Nuclear Information System (INIS)

KSC-1 (KAERI Shipping Cask-1) was designed and manufactured with a pure domestic technology in 1985 in order to transport a PWR spent fuel assembly from nuclear power plant to PIEF (Post-Irradiation Examination Facility) of KAERI. Since the first transportation of the fuel assembly from Kori-1 NPP was carried out by the cask in 1987, 19 shipments for the PWR spent fuels have been done successfully by now. Maximum discharge burnup of PWR in Korea has been extended from the late 1990s in order to reduce the cost of power generation. From this cause, allowable design values of the initial enrichment and the cooling time for the cask have been changed three times: year 2003, 2007 and 2010. Radiation shielding and criticality of KSC-1 were analyzed for all the PWR fuel type irradiated in Korea NPP to renew the design approval

2010-10-01

139

Waste Handling Shaft concrete liner degradation conclusions and recommendations  

International Nuclear Information System (INIS)

The primary function of the Waste Handling Shaft (WHS) at the Waste Isolation Pilot Plant (WIPP) is to permit the transfer of radioactive waste from the surface waste handling building to the underground storage area. It also serves as an intake shaft for small volumes of air during normal storage operations and as an emergency escape route. Part of the construction was the placement of a concrete liner and steel reinforced key in 1984. During a routine shaft inspection in May 1990, some degradation of the WHS concrete liner was observed between the depths of 800 and 900 feet below the ground surface. Detailed investigations of the liner had been carried out by Sandia National Laboratories and by Westinghouse Electric Corporation Waste Isolation Division (WID) through Lankard Materials Laboratory. Observations, reports, and data support the ...

140

Determination of the helium thermal diffusion coefficient in britholite using a NRA method: new results  

International Nuclear Information System (INIS)

Dimensioning of actinides waste packages for long duration storage has to take into account helium production from natural decay and release rates from the material. For the latter, we propose here an improved method for the determination of the helium diffusion coefficient in britholite, to be used for minor actinides storage. This work is based on results we previously published using the classical three steps method: "3He implantation on a Van de Graaff facility, "3He profile determination analysing the protons resulting from the "3He(d,p)"4He reaction in a nuclear microprobe, evolution of the helium profile during annealings. Taking explicitly into account the incident deuterons energy stragglings allows us to show that the implanted helium profiles are bimodal, each component leading to a different helium diffusion coefficient.

2005-02-01

141

Concentration of Melton Valley Storage Tank surrogates with a wiped film evaporator  

Energy Technology Data Exchange (ETDEWEB)

This report describes experiments to determine whether a wiped film evaporator (WFE) might be used to concentrate low-level liquid radioactive waste (LLLW). Solutions used in these studies were surrogates that contain no radionuclides. The compositions of the surrogates were based on one of Oak Ridge National Laboratory`s (ORNL`s) Melton Valley Storage Tanks (MVSTs). It was found that a WFE could be used to concentrate LLLW to varying degrees by manipulating various parameters. The parameters studied were rotor speed, process fluid feed temperature and feed rate, and evaporator temperature. Product consistency varied from an unsaturated liquid to a dry powder. Volume reductions up to 68% were achieved. System decontamination factors were consistently in the range of 10{sup 4}.

1994-08-01

142

Update of the management strategy for Oak Ridge National Laboratory Liquid Low-Level Waste  

Energy Technology Data Exchange (ETDEWEB)

The strategy for management of the Oak Ridge National Laboratory`s (ORNL) radioactively contaminated liquid waste was reviewed in 1991. The latest information available through the end of 1990 on waste characterization, regulations, US Department of Energy (DOE) budget guidance, and research and development programs was evaluated to determine how the strategy should be revised. Few changes are needed to update the strategy to reflect new waste characterization, research, and regulatory information. However, recent budget guidance from DOE indicates that minimum funding will not be sufficient to accomplish original objectives to upgrade the liquid low-level waste (LLLW) system to comply with the Federal Facilities Agreement, provide long-term LLLW treatment capability, and minimize environmental, safety, and health risks. Options are presented that might allow the ORNL LLLW system to continue operations ...

1995-04-01

143

Status of the ORNL liquid low-level waste management upgrades  

Energy Technology Data Exchange (ETDEWEB)

The strategy for management of the Oak Ridge National Laboratory`s (ORNL`s) radioactively contaminated liquid waste was reviewed. The latest information on waste characterization, regulations, US Department of Energy (DOE) budget guidance, and research and development programs was evaluated to determine how the strategy should be revised. Few changes are needed to update the strategy to reflect new waste characterization, research, and regulatory information. However, recent budget guidance from DOE indicates that minimum funding will not be sufficient to accomplish original objectives to upgrade the liquid low-level waste (LLLW) system to be in compliance with the Federal Facilities Agreement compliance, provide long-term LLLW treatment capability, and minimize Environmental Safety & Health risks. Options are presented that might allow the ORNL LLLW system to continue operations temporarily but ...

1995-08-01

144

DOE assay methods used for characterization of contact-handled transuranic waste  

International Nuclear Information System (INIS)

US Department of Energy methods used for characterization of contact-handled transuranic (CH-TRU) waste prior to shipment to the Waste Isolation Pilot Plant (WIPP) are described and listed by contractor site. The methods described are part of the certification process. All CH-TRU waste must be assayed for determination of fissile material content and decay heat values prior to shipment and prior to storage on-site. Both nondestructive assay (NDA) and destructive assay methods are discussed, and new NDA developments such as passive-action neutron (PAN) crate counter improvements and neutron imaging are detailed. Specifically addressed are assay method physics; applicability to CH-TRU wastes; calibration standards and implementation; operator training requirements and practices; assay procedures; assay precision, bias, and limit of detection; and assay limitation. While PAN is a new ...

145

DOE assay methods used for characterization of contact-handled transuranic waste  

Energy Technology Data Exchange (ETDEWEB)

US Department of Energy methods used for characterization of contact-handled transuranic (CH-TRU) waste prior to shipment to the Waste Isolation Pilot Plant (WIPP) are described and listed by contractor site. The methods described are part of the certification process. All CH-TRU waste must be assayed for determination of fissile material content and decay heat values prior to shipment and prior to storage on-site. Both nondestructive assay (NDA) and destructive assay methods are discussed, and new NDA developments such as passive-action neutron (PAN) crate counter improvements and neutron imaging are detailed. Specifically addressed are assay method physics; applicability to CH-TRU wastes; calibration standards and implementation; operator training requirements and practices; assay procedures; assay precision, bias, and limit of detection; and assay limitation. While PAN is a new ...

1991-08-01

146
147

Should high-level nuclear waste be disposed of at geographically dispersed sites?  

Energy Technology Data Exchange (ETDEWEB)

Consideration of the technical feasibility of Yucca Mountain in Nevada as the site for a high-level nuclear waste repository has led to an intense debate regarding the economic, social, and political impacts of the repository. Impediments to the siting process mean that the nuclear waste problem is being resolved by adhering to the status quo, in which nuclear waste is stored at scattered sites near major population centers. To assess the merits of alternative siting strategies--including both the permanent repository and the status quo- we consider the variables that would be included in a model designed to select (1) the optimal number of disposal facilities, (2) the types of facilities (e.g., permanent repository or monitored retrievable facility), and (3) the geographic location of storage sites. The objective function in the model is an all-inclusive measure of social cost. The intent of the ...

1992-07-01

148

Integration of advanced nuclear materials separation processes  

Energy Technology Data Exchange (ETDEWEB)

This is the final report of a two-year, Laboratory Directed Research and Development (LDRD) project at the Los Alamos National Laboratory (LANL). This project has examined the fundamental chemistry of plutonium that affects the integration of hydrothermal technology into nuclear materials processing operations. Chemical reactions in high temperature water allow new avenues for waste treatment and radionuclide separation.Successful implementation of hydrothermal technology offers the potential to effective treat many types of radioactive waste, reduce the storage hazards and disposal costs, and minimize the generation of secondary waste streams. The focus has been on the chemistry of plutonium(VI) in solution with carbonate since these are expected to be important species in the effluent from hydrothermal oxidation of Pu-containing organic wastes. The authors investigated the ...

1998-12-31

149

EDF waste packages transport and compliance with regulations: prediction of retention of radionuclides by cementitious materials  

International Nuclear Information System (INIS)

Different concrete waste packages have been designed by Electricite de France (EDF) for the long-term storage of radioactive Low Level Waste (LLW). Their main function is to confine radionuclides from the biosphere for three hundred years in a near-surface disposal. According to the transport regulations, a Type-B package is needed for some waste like water filters. The water filters from EDF nuclear power plants are encapsulated in mortar and placed in a concrete container. Transport regulations for these containers have required the development of a methodology for safety assessment. The reference scenario of container degradation during transport considers a 9 m drop and a 800"oC fire for 30 min. First, the different chemical and physical processes involved in the containment of radionuclides are analysed. In particular, the radionuclide transport mechanisms in cement-based materials have been ...

150

Research by ESS Division for the Nevada Nuclear Waste Storage Investigations: Progress report, January-June 1985  

Energy Technology Data Exchange (ETDEWEB)

Petrographic research for the Nevada Nuclear Waste Storage Investigations focused on xenolithic variability in the Topopah Spring Member and on variations of clinoptilolite composition at Yucca Mountain. Zeolite and smectite occurrences were considered in terms of their relation to a disturbed zone beneath the potential repository, and mineral stability experiments have produced a new clinoptilolite structure as a result of prolonged heating at low temperature. Limitations were defined on the abundance of erionite and of sulfur. X-ray diffraction studies lead to improved analytical methods. Progress was made in the comparative study of mineralogy in sand ramps and in faults. Geological modeling considered the differences of the diffusion of nonsorbing tracers in vertically and in horizontally fractured rock. Modeling also treated the diffusion of a nonsorbing tracer in devitrified and in zeolitized rock. The results of these experiments in all ...

1987-10-01

151

Nuclear power and sustainable development  

International Nuclear Information System (INIS)

In Romania, the nuclear power is an element of sustainable development, being competitive, efficient and viable in the market economy. Fuel supply is ensured as nuclear fuel is manufactured in the country out of local uranium resources available in Romania. As for the environmental protection, it is known that, unlike the thermal power plants, the nuclear power plants do not release sulfur and nitrogen oxides, carbon dioxide and do not generate slag and ashes. The operation of nuclear power units does not release pollutants and, accordingly, these stations can contribute to the limitation and the abatement of environmental pollution. After seven years of Cernavoda NPP Unit 1 operation, a facility for storing low and medium level nuclear fuel wastes was built at the plant site as well as an intermediate dry storage for spent nuclear fuel whose first modules were commissioned in July 2003. They shall provide safe storage ...

2003-07-01

152

Methanogens and sulfate-reducing bacteria in oil sands fine tailings waste.  

Science.gov (United States)

In the past decade, the large tailings pond (Mildred Lake Settling Basin) on the Syncrude Canada Ltd. lease near Fort McMurray, Alta., has gone methanogenic. Currently, about 60%-80% of the flux of gas across the surface of the tailings pond is methane. As well as adding to greenhouse gas emissions, the production of methane in the fine tailings zone of this and other settling basins may affect the performance of these settling basins and impact reclamation options. Enumeration studies found methanogens (10(5)-10(6) MPN/g) within the fine tailings zone of various oil sands waste settling basins. SRB were also present (10(4)-10(5) MPN/g) with elevated numbers when sulfate was available. The methanogenic population was robust, and sample storage up to 9 months at 4 degrees C did not cause the MPN values to change. Nor was the ability of the consortium to produce methane delayed or less efficient after storage. Under ...

2000-10-01

153

Economic analysis of fuel recycle  

International Nuclear Information System (INIS)

Economic analysis was performed at KAERI with the assistance of US DOE to compare single reactor fuel cycle costs for a once-through option and a thermal recycle option to operate 1 GWe of a PWR plant for its lifetime. A reference fuel cycle cost was first calculated for each option with best estimated reference input data. Then a sensitivity analysis was performed changing each single value of such fuel cycle component costs as yellow cake price, enrichment charges, spent fuel storage cost, reprocessing cost, spent fuel disposal cost and reprocessing waste disposal cost. Savings due to thermal recycle in requirements of uranium, conversion, and enrichment were examined using formulas suggested by US DOE, while MOX fabrication penalty was accounted for. As a result of the reference fuel cycle cost analysis, it is calculated that the thermal recycle option is marginally more economical than the once-through option. The major factors affecting ...

1985-05-19

154

Waste management plan for Phase II of the Bear Creek Valley treatability study Oak Ridge Y-12 Plant, Oak Ridge, Tennessee  

Energy Technology Data Exchange (ETDEWEB)

This Waste Management Plant (WMP) for the Bear Creek Valley Treatability Study addresses waste management requirements for the Oak Ridge Y-12 Plant. The study is intended to produce treatment performance data required to design a treatment system for contaminated groundwater. The treatability study will consist of an evaluation of various treatment media including: continuous column tests, with up to six columns being employed to evaluate the performance of different media in the treatment of groundwater; an evaluation of the denitrifying capacity and metal uptake capacity of a wetland system; and the long-term denitrifying capacity and metal uptake capacity of algal mats. The Sampling and Analysis Plan (SAP) covers the project description, technical objectives, procedures, and planned work activities in greater detail. The Health and Safety Plan (HASP) addresses the health and safety concerns and requirements for the proposed sampling ...

1997-05-01

155

REGULATIONS ON PHOTOVOLTAIC MODULE DISPOSAL AND RECYCLING.  

Energy Technology Data Exchange (ETDEWEB)

Environmental regulations can have a significant impact on product use, disposal, and recycling. This report summarizes the basic aspects of current federal, state and international regulations which apply to end-of-life photovoltaic (PV) modules and PV manufacturing scrap destined for disposal or recycling. It also discusses proposed regulations for electronics that may set the ground of what is to be expected in this area in the near future. In the US, several states have started programs to support the recycling of electronic equipment, and materials destined for recycling often are excepted from solid waste regulations during the collection, transfer, storage and processing stages. California regulations are described separately because they are different from those of most other states. International agreements on the movement of waste between different countries may pose barriers to cross-border shipments. Currently ...

2001-01-29

156

Nevada Test Site 2007 Data Report: Groundwater Monitoring Program Area 5 Radioactive Waste Management Site  

Science.gov (United States)

This report is a compilation of the groundwater sampling results from three monitoring wells located near the Area 5 Radioactive Waste Management Site (RWMS) at the Nevada Test Site (NTS), Nye County, Nevada, for calendar year 2007. The NTS is an approximately 3,561 square kilometer (1,375 square mile) restricted-access federal installation located approximately 105 kilometers (65 miles) northwest of Las Vegas, Nevada (Figure 1). Pilot wells UE5PW-1, UE5PW-2, and UE5PW-3 are used to monitor the groundwater at the Area 5 RWMS (Figure 2). In addition to groundwater monitoring results, this report includes information regarding site hydrogeology, well construction, sample collection, and meteorological data measured at the Area 5 RWMS. The disposal of low-level radioactive waste and mixed low-level radioactive waste at the Area 5 RWMS is regulated by U.S. Department of Energy (DOE) Order 435.1, 'Radioactive ...

2008-01-01

157

Standardization/improvement and technical development of light water reactor power station in Japan(BWR)  

Energy Technology Data Exchange (ETDEWEB)

In order to realize improve of reliability and economy by duplicate production, rapid supply of repair parts from standardized storage, such were expected as to have continuous order of standardized plant, to ignore site condition, to avoid expansion of regulatory requirement. Standardization program was planned to limitedly promote standardization of safety-related design concept, major specification and basic system composition of reactor and primary systems. The area of standardization had been tried to expand to BOP such as general arrangement and rad-waste system.

1985-07-01

158

Scientific reference on the long time evolution of spent fuels; Referentiel scientifique sur l'evolution a long terme des combustibles uses  

Energy Technology Data Exchange (ETDEWEB)

This report is published in the framework of the 1991 French law for the nuclear waste management. The state of the art reported here concerns the long term evolution of spent fuel in the various environmental conditions corresponding to dry storage and geological disposal: closed system, air and water saturated medium. This review is based on the results of the french PRECCI project (Research Program on Long term Evolution of Spent Nuclear Fuel) and on literature data. (authors)

2005-03-15

159

Review on the status of solid radwaste management in Korean NPPs  

International Nuclear Information System (INIS)

To minimize the low and intermediate-level solid radwaste volume, the reduction efforts were persisted in Korean NPPs. As a result, annual average waste volumes were reduced to 194 drums per unit at last year. In this paper we confirmed 250 drums/unit-yr, EPRI URD management goal, and management condition for solid radwaste volume. Also, through the sample assessment of specific Korean NPP opened to the public, we could make sure that the prediction of saturation year for interim storage facility is fully suitable.

2003-10-01

160

R&D prioritization and resource management for technology selection  

Energy Technology Data Exchange (ETDEWEB)

This paper presents a decision approach, and associated computer software tools, for prioritizing and selecting among technology development activities. The approach elicits and then summarizes technology development preferences from stakeholders, and then integrates preferences into a set of funding recommendations. By formalizing the technology review process, the decision approach builds consensus and clarifies the basis for final budget decisions. The software development was conducted jointly by Pacific Northwest Laboratory and Decisions Science Associates, Incorporated. The Underground Storage Tank Integrated Demonstration funded the task; however, the approach should also be valuable to the US Department of Energy Office of Technology Development, the Office of Waste Management, and the Office of Environmental Restoration.

1994-03-01

161

Proceedings of the Canadian Society for Bioengineering CSBE/SCGAB 2008 annual meeting  

Energy Technology Data Exchange (ETDEWEB)

This conference provided a forum to discuss advances in the application of bioengineering principles and practices dealing with biological systems for the production of food, bioproducts and energy. The topics of discussion ranged from engineering practices in agriculture, forestry, bioresources, biochemistry and biosystems. The sessions of the conference were entitled: renewable energy; waste management; soil and water; machinery systems; building and storage systems; and bioproducts and food. The conference also featured a workshop on integrated biomass supply and logistics. In addition to 20 posters, the conference featured 67 presentations, of which 3 have been catalogued separately for inclusion in this database. refs., tabs., figs.

2008-07-01

162

Bringing robotics technology down to Earth  

International Nuclear Information System (INIS)

Robotics technology is successfully being transitioned from space to terrestrial applications. It is being modified and enhanced to help in the US DOE's Environmental Restoration and Waste Management Program. Some examples of these applications, ranging from large multijointed manipulators to autonomously navigated remote vehicles, are outlined in this article. They include the following: underground storage tank technology demonstration; light-duty utility arm system; remotely controlled material-handling system; remotely operated excavator; self-guided transfer vehicle. 10 figs.

163

Actions for the environment  

CERN Document Server

As an International Organization, one the most important issues that CERN has to respect and guarantee is the protection of the environment. Several of ST activities and operations have a direct impact on the environment: civil engineering works, electrical (transformers) and air-cooling operation, chemical products storage, various waste disposal etc.... Important measures, taken in the past, have to be kept and new ones should be applied in order to insure the conformity of the infrastructure with existing legislation, the correct operation of equipment and systems, the constant monitoring of the different situations and the traceability of the events. Moreover good management of the environment would bring large savings to CERN.

2003-01-01

164

Maintenance implementation plan for the B Plant/WESF. Revision 4  

Energy Technology Data Exchange (ETDEWEB)

This Maintenance Implementation Plan (MIP) has been developed for maintenance functions associated with the B Plant/WESF (Waste Encapsulation Storage Facility) complex. The objective of this plan is to provide baseline information for establishing and identifying WHC conformance programs and policies applicable to implementation of DOE order 4330.4B guidelines. In addition, this maintenance plan identifies the actions necessary to develop a cost-effective and efficient maintenance program at B Plant/WESF. The B Plant WESF facility complex consists of three main facilities and several support structures located in the 200 East Area of the Hanford site. B Plant is a transition facility that is required to ensure safe storage and management of WESF (operating facility) cesium and strontium capsules. B Plant/WESF also contains substantial radiological inventory from previous campaigns. There are no production activities at B ...

1996-01-01

165

Nuclear cask testing films misleading and misused  

Energy Technology Data Exchange (ETDEWEB)

In 1977 and 1978, Sandia National Laboratories, located in Albuquerque, New Mexico, and operated for the US Department of Energy (DOE), filmed a series of crash and fire tests performed on three casks designed to transport irradiated nuclear fuel assemblies. While the tests were performed to assess the applicability of scale and computer modeling techniques to actual accidents, films of them were quickly pressed into service by the DOE and nuclear utilities as proof'' to the public of the safety of the casks. In the public debate over the safety of irradiated nuclear fuel transportation, the films have served as the mainstay for the nuclear industry. Although the scripts of all the films were reviewed by USDOE officials before production, they contain numerous misleading concepts and images, and omit significant facts. The shorter versions eliminated qualifying statements contained in the longer version, and created false ...

1991-10-01

166

Status and strategies in radioactive waste management in the Russian Federation  

International Nuclear Information System (INIS)

Full text: There are following general tendencies linking to SNF and radioactive waste management (RWM) in the Russian nuclear industry now. The intention to use the closed nuclear fuel cycle based on power water reactors and fast reactor. The intensification of measures aimed at the solution of 'nuclear legacy' from defenses programs of USSR. The intention to improve the existing national RW management infrastructure in the near years by means of the creation of a centralized national system (including managing corporation responsible for operation of long-storage and disposal facilities of conditioned RW). The main aims radioactive waste management (RWM) in nuclear power plants (NPP) for the next 10-15 years are to equip all NPPs with the necessary set of facilities for conditioning of the stored and currently generated RW with packaging the end-product into containers, to build regional NPPs RW repositories and to ...

167

Drying plant waste; Trocknung von Betriebsabfaellen  

Energy Technology Data Exchange (ETDEWEB)

Under the repository storage conditions of Eram and Konrad, waste packages designed for permanent storage must not contain or release freely mobile liquids, except for the minimum residues attainable by reasonable efforts or unavoidable. In accordance with a directive issued by the German Federal Ministry for the Environment (BMU), waste conditioning must be carried out so as to minimize waste volumes and, if possible, on the site where the waste arises. Liquid waste is conditioned most effectively by drying. At the present time, various different processes for drying liquid waste are employed as reflected by the state of the art: The Robe process; roller drying; the RDA process; Favorit; in-drum drying; and HPA liquid waste drying with make-up feed. The HPA process offers these advantages: Drying ...

1995-11-01

168

Water and oxygen transfer in a waste rock pile constructed by mixing layers; Transfert de l'eau et de l'oxygene dans une halde de steriles construite par entremelement par couches  

Energy Technology Data Exchange (ETDEWEB)

Acid mine drainage represents one of the most important environmental problem facing the mining industry. If the tailings contain sulphur, acid mine drainage will be generated as soon as the tailings are exposed to oxygen. In this paper, the authors discussed a technique for the storage of acid mine drainage generating tailings that delays and even eliminates the occurrence. It was suggested that tailings should be piled by incorporating, at regular intervals, compacted waste rock. Thermal convection and diffusion will prevent oxygen from reaching the tailings, and limit water circulation. The modelling of transfer processes (heat, water, oxygen) in a well known tailings dump, the Doyon Mine, was performed, and the results compared to the modelling where compacted waste rock had been incorporated at regular intervals. The results indicated that by remaining saturated, the layers acted as capillary barriers preventing oxygen ...

2000-07-01

169

Waste sampling and characterization facility (WSCF)  

Energy Technology Data Exchange (ETDEWEB)

The Waste Sampling and Characterization Facility (WSCF) complex consists of the main structure (WSCF) and four support structures located in the 600 Area of the Hanford site east of the 200 West area and south of the Hanford Meterology Station. WSCF is to be used for low level sample analysis, less than 2 mRem. The Laboratory features state-of-the-art analytical and low level radiological counting equipment for gaseous, soil, and liquid sample analysis. In particular, this facility is to be used to perform Resource Conservation and Recovery Act (RCRA) of 1976 and Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) of 1980 sample analysis in accordance with U.S. Environmental Protection Agency Protocols, room air and stack monitoring sample analysis, waste water treatment process support, and contractor laboratory quality assurance checks. The samples to be analyzed contain very low concentrations of radioisotopes. The ...

1994-10-01

170

The carbon balance and greenhouse effects of the Finnish forest sector at present, in the past and future  

Energy Technology Data Exchange (ETDEWEB)

In this study the greenhouse impact of the total Finnish forest sector was considered, which means that the estimated emissions and sink effects from exported forest products were also included. The forest biomass is and seems to be in the next decades the most important factor in the carbon balance of the total forest sector. The development alternatives of forest industries and waste management practices has still a remarkable influence on the greenhouse impact of the Finnish forest sector. The waste management practices in the future has an important influence on the emissions but the exact net greenhouse impact of the landfills is still uncertain. However, the methane emissions from existing landfills can be reduced essentially by gas recovery. Increased incineration and energy recovery of wood waste (and replacing fossil fuel use by it) is also a future alternative for reducing the greenhouse effects in the forest ...

1996-12-31

171

Nevada Nuclear Waste Storage Investigations: Exploratory Shaft Facility fluids and materials evaluation  

Energy Technology Data Exchange (ETDEWEB)

The objective of this study was to determine if any fluids or materials used in the Exploratory Shaft Facility (ESF) of Yucca Mountain will make the mountain unsuitable for future construction of a nuclear waste repository. Yucca Mountain, an area on and adjacent to the Nevada Test Site in southern Nevada, USA, is a candidate site for permanent disposal of high-level radioactive waste from commercial nuclear power and defense nuclear activities. To properly characterize Yucca Mountain, it will be necessary to construct an underground test facility, in which in situ site characterization tests can be conducted. The candidate repository horizon at Yucca Mountain, however, could potentially be compromised by fluids and materials used in the site characterization tests. To minimize this possibility, Los Alamos National Laboratory was directed to evaluate the kinds of fluids and materials that will be used and their potential impacts on the site. A ...

1988-11-01

172

Fifty years of federal radioactive waste management: Policies and practices  

Energy Technology Data Exchange (ETDEWEB)

This report provides a chronological history of policies and practices relating to the management of radioactive waste for which the US Atomic Energy Commission and its successor agencies, the Energy Research and Development Administration and the Department of Energy, have been responsible since the enactment of the Atomic Energy Act in 1946. The defense programs and capabilities that the Commission inherited in 1947 are briefly described. The Commission undertook a dramatic expansion nationwide of its physical facilities and program capabilities over the five years beginning in 1947. While the nuclear defense activities continued to be a major portion of the Atomic Energy Commission`s program, there was added in 1955 the Atoms for Peace program that spawned a multiplicity of peaceful use applications for nuclear energy, e.g., the civilian nuclear power program and its associated nuclear fuel cycle; a variety of industrial applications; and medical research, ...

1997-04-01

173

BIBRA "t"r"a"d"e"m"a"r"k - the biological treatment of radioactive waste water  

International Nuclear Information System (INIS)

BIBRA "t"r"a"d"e"m"a"r"k, is the new bio-technological method developed in Gundremmingen for treating radioactive waste water, using bacteria in a process analogous to the long-established principle of communal sewage treatment plants. The method exploits the behaviour of the micro-organisms found there, to establish optimum adaptation of their population for decomposing the typical pollutants found in this washing water. This procedure is particularly suitable for nuclear engineering plants, because in such plants the waste water composition changes little so that the bacteria can achieve optimum adaptation to this waste water. The organic ingredients of the washing media are decomposed by introducing air. The advantage of the procedure is not only the significant reduction of the amount of waste material, but also enhanced efficiency of the cleaning process. The decontamination factor in Gundremmingen ...

1999-03-01

174

Decommissioning of French nuclear submarines  

Energy Technology Data Exchange (ETDEWEB)

Since the beginning of the sixties, France has developed a fleet of nuclear powered vessels. Insofar as the ships of the 2. generation are being built, the older ones are decommissioned and enter the dismantling process. The average rate is presently one submarine decommissioned every two or three years. The overall strategy for the decommissioning of French nuclear submarines can be brought down to 3 phases: 1. Level 1 dismantling which essentially consists in: - unloading the spent fuel and storing it in a pool ; - possibly emptying the circuits which contain radioactive liquids. The level 1 is easily achieved, as it is not very different from the plant situation during ship overhaul or major refits. 2. Level 2 dismantling which consists in isolating the nuclear reactor compartment from the rest of the submarine and conditioning it for interim storage on a ground facility located inside Cherbourg Naval Dockyard. The rest of the ship is decontaminated, controlled ...

2003-07-01

175

The Principles of Radioactive Waste Management  

CERN Document Server

The Principles of Radioactive Waste Management

1995-01-01

176

Establishing a nationalsystem for radioactive waste management  

CERN Document Server

Establishing a nationalsystem for radioactive waste management

1995-01-01

177

EFFECTS OF QUARTZ PARTICLE SIZE AND SUCROSE ADDITION ON MELTING BEHAVIOR OF A MELTER FEED FOR HIGH-LEVEL GLASS  

Energy Technology Data Exchange (ETDEWEB)

The behavior of melter feed (a mixture of nuclear waste and glass-forming additives) during waste-glass processing has a significant impact on the rate of the vitrification process. We studied the effects of silica particle size and sucrose addition on the volumetric expansion (foaming) of a high-alumina feed and the rate of dissolution of silica particles in feed samples heated at 5 C/min up to 1200 C. The initial size of quartz particles in feed ranged from 5 to 195 {micro}m. The fraction of the sucrose added ranged from 0 to 0.20 g per g glass. Extensive foaming occurred only in feeds with 5-{micro}m quartz particles; particles {ge}150 {micro}m formed clusters. Particles of 5 {micro}m completely dissolved by 900 C whereas particles {ge}150 {micro}m did not fully dissolve even when the temperature reached 1200 C. Sucrose addition had virtually zero impact on both foaming and the dissolution of silica particles. Over 100 sites in the United ...

2010-07-28

178

Waste to energy technologies.  

Science.gov (United States)

No abstract prepared.

2010-04-01

179

Energy Conversion and Storage Program: 1992 Annual report  

Energy Technology Data Exchange (ETDEWEB)

This report is the 1992 annual progress report for the Energy Conversion and Storage Program, a part of the Energy and Environment Division of the Lawrence Berkeley Laboratory. Work described falls into three broad areas: electrochemistry; chemical applications; and materials applications. The Energy Conversion and Storage Program applies principles of chemistry and materials science to solve problems in several areas: (1) production of new synthetic fuels, (2) development of high-performance rechargeable batteries and fuel cells, (3) development of advanced thermochemical processes for energy conversion, (4) characterization of complex chemical processes and chemical species, and (5) study and application of novel materials for energy conversion and transmission. Projects focus on transport-process principles, chemical kinetics, thermodynamics, separation processes, organic and physical chemistry, novel materials, and advanced methods of ...

1993-06-01

180

Energy Conversion and Storage Program. 1990 annual report  

Energy Technology Data Exchange (ETDEWEB)

The Energy Conversion and Storage Program applies chemistry and materials science principles to solve problems in (1) production of new synthetic fuels, (2) development of high-performance rechargeable batteries and fuel cells, (3) development of advanced thermochemical processes for energy conversion, (4) characterization of complex chemical processes, and (5) application of novel materials for energy conversion and transmission. Projects focus on transport-process principles, chemical kinetics, thermodynamics, separation processes, organic and physical chemistry, novel materials, and advanced methods of analysis. Electrochemistry research aims to develop advanced power systems for electric vehicle and stationary energy storage applications. Topics include identification of new electrochemical couples for advanced rechargeable batteries, improvements in battery and fuel-cell materials, and the establishment of engineering principles applicable ...

1992-03-01

181

Energy Conversion and Storage Program  

Energy Technology Data Exchange (ETDEWEB)

The Energy Conversion and Storage Program applies chemistry and materials science principles to solve problems in (1) production of new synthetic fuels, (2) development of high-performance rechargeable batteries and fuel cells, (3) development of advanced thermochemical processes for energy conversion, (4) characterization of complex chemical processes, and (5) application of novel materials for energy conversion and transmission. Projects focus on transport-process principles, chemical kinetics, thermodynamics, separation processes, organic and physical chemistry, novel materials, and advanced methods of analysis. Electrochemistry research aims to develop advanced power systems for electric vehicle and stationary energy storage applications. Topics include identification of new electrochemical couples for advanced rechargeable batteries, improvements in battery and fuel-cell materials, and the establishment of engineering principles applicable ...

1992-03-01

182

Photon storage cavities  

Energy Technology Data Exchange (ETDEWEB)

A general analysis is presented of a photon storage cavity, coupled to free-electron laser (FEL) cavity. It is shown that if the coupling between the FEL cavity and the storage cavity is unidirectional (for example, a ring resonator storage cavity) then storage is possible, but that if the coupling is bi-directional then storage is not possible. Parameters are presented for an infra-red FEL storage cavity giving an order of magnitude increase in the instantaneous photon power within the storage cavity. 4 refs., 3 figs.

1991-08-01

183

A shockproof container for the transport and storage of fragile or reactive target foils  

CERN Document Server

A shockproof container for the transport and storage of fragile or reactive target foils

1971-01-01

184

Radiological assessment of terrestrial environment of facilities of G.I.P. CYCERON from Caen - year 2003; Bilan radiologique de l'environnement terrestre des installations du GIP CYCERON de Caen - annee 2003  

Energy Technology Data Exchange (ETDEWEB)

Concerning the gamma emitters, the only analysis on soils put in evidence the presence of cesium-137 ({sup 137}Cs), that does not come from the cyclotron functioning but from past man action as the Chernobylsk accident and the nuclear weapon tests in atmosphere. Independently of the functioning of the installation, we observe an increase of the ambient gamma radiation only near radioactive waste storage. It results of the storage of the former cyclotron elements. The induced increase is moderated because at 5 meters the values do not exceed the background noise. In relation with the functioning of the installation an increase of the ambient gamma radiation is noticed. Two causes are to considered: the release of radionuclides in atmosphere with gaseous effluents and the radiance of radiation sources inside the building. After the stopping of the installation (48 h at least), no increase of gamma radiation is observed. About ...

2004-07-01

185

Overview of the 1995 NATO ARW on nuclear submarine decommissioning and related problems  

International Nuclear Information System (INIS)

The NATO Advanced Research Workshop on Nuclear Submarine Decommissioning and Related Problems was held in Moscow June 19--22, 1995. It was preceded by a visit to the Zvezdotchka Shipyard at Severodvinsk, a repair and maintenance yard for Russian nuclear submarines, for a subgroup of the workshop attendees. Most of the material in this paper is drawn directly form the workshop proceedings. Slightly less than 500 nuclear ships and submarines (the vast majority are submarines) have been constructed by the countries with nuclear navies. This includes approximately 250 by Russia, 195 by the United States, 23 by the United Kingdom, 11 by France and 6 by China. By the year 2000 it is expected that approximately one-half of these nuclear vessels will be removed from service and in various states of decommissioning. A newspaper account in June 1997 indicated that 156 Russian nuclear submarines had been removed from service. In August 1996 it was reported that 55 reactor compartment sections ...

1997-11-21

186

UK regulations for NORM [naturally occurring radioactive material  

International Nuclear Information System (INIS)

The primary UK legislation relating to the use of radioactive materials are the Radioactive Substances Act 1993 (RSA, 1993) and the Ionising Radiations Regulations 1999 (IRR, 1999). These implement the European Union's Basic Safety Standards Directive (EUBSS) (EC, 1996). The Radioactive Substances Act 1993 (RSA93) regulates the accumulation, storage and disposal of radioactive waste, principally to control potential doses to members of the public. The Ionising Radiations Regulations 1999 (IRR, 1999) deal primarily with regulating the doses that people receive at work. Both of these pieces of legislation apply to the use of materials containing naturally occurring radionuclides. Historically UK regulations relating to radioactive materials have covered both artificial and natural radionuclides

2002-09-23

187

UK Achievements in the application of power fluidic technology for nuclear processing plants  

International Nuclear Information System (INIS)

Power Fluidic systems for the control of liquids and gaseous flows have been adopted for use in radioactive processing plants in the UK. These devices are intrinsically reliable with no mechanical moving parts because they are able to make use of the hydrodynamics of the fluids being controlled. This reliability feature leads to a zero cell maintenance concept and the elimination of mechanical drive/control systems in cell. The first phase of the development work led to their use in the Fast Reactor Reprocessing Plant at Dounreay and the Highly Active Liquor Storage facility at Sellafield. The success of these early developments has led to an extensive development programme for an extended range of applications in the Thermal Oxide Reprocessing Plant and its associated waste treatment facilities at Sellafield. The technology has now been fully demonstrated and adopted for these plants with considerable benefit over a wide range of applications.

188

Technical evaluation report for the demonstration of radio frequency soil decontamination at Site S-1  

Energy Technology Data Exchange (ETDEWEB)

The Air Force`s Armstrong Laboratory at Tyndall Air Force Base, Florida, has supported the research and development of Radio Frequency Soil Decontamination. Radio frequency soil decontamination is essentially a heat-assisted soil vapor extraction process. Site S-1 at Kelly Air Force Base, San Antonio, Texas, was selected for the demonstration of two patented techniques. The site is a former sump that collected spills and surface run-off from a waste petroleum, oils, and lubricants and solvent storage and transfer area. In 1993, a technique developed by the IIT Research Institute using an array of electrodes placed in the soil was demonstrated. In 1994, a technique developed by KAI Technologies, Inc. using a single applicator placed in a vertical borehole was demonstrated. Approximately 120 tons of soil were heated during each demonstration to a temperature of about 150 degrees Celsius.

1995-04-01

189

Proceedings of the Canadian Society for Bioengineering CSBE/SCGAB 2006 national technical conference  

Energy Technology Data Exchange (ETDEWEB)

This conference provided a forum for discussing advances in the application of engineering principles and practices dealing with biological systems for the production of food, bioproducts and energy. The discussions focused on engineering practices in agriculture, forestry, bioresources, biochemistry and biosystems. The sessions of the conference were entitled: renewable energy and biofuels; food and bioproducts; odour and greenhouse gases; soil and water; waste management and bioresiduals; animal welfare and production; grain storage; machinery systems; structures and biocomposites; and, agricultural production. The conference also featured a workshop on modeling material and energy flows through agro-ecosystems. In addition to 22 posters, the conference featured 100 presentations, of which 8 have been catalogued separately for inclusion in this database. refs., tabs., figs.

2006-07-01

190

Energy threat to valuable land  

Energy Technology Data Exchange (ETDEWEB)

A negative public reaction is expected to oppose plans of the British energy industry to take valuable sites for industrial and commercial projects on the ground that government demand forecasts are too high and that they downplay conservation. The United Kingdom (UK) Department of Energy points out that public inquiry always accompanies energy installations and defends the projections made by producers even though each study emphasizes the demand for its own form of energy. At issue are plans to open 150 opencast coal mines a year to compensate for diminishing oil and gas supplies, onshore drilling by oil and gas exploration teams on nearly 50,000 km/sup 2/, and sites required for onshore pipelines, synthetic natural gas facilities, pumped storage plants, and nuclear power stations and waste management. The sites under discussion raise aesthetic and ecological concerns. (DCK)

1982-03-11

191

Burning nuclear wastes in fusion reactors  

Energy Technology Data Exchange (ETDEWEB)

We have studied actinide burn-up in ICF reactor pellets; i.e., 14 MeV neutron fission of the very long-lived actinides that pose storage problems. A major advantage of pellet fuel region burn-up is safety: only milligrams of highly toxic and active material need to be present in the fusion chamber, whereas blanket burn-up requires the continued presence of tons of actinides in a small volume. The actinide data tables required for Monte Carlo calculations of the burn-up of /sup 241/Am and /sup 243/Am are discussed in connection with a study of the sensitivity to cross section uncertainties. More accurate and complete cross sections are required for realistic quantitative calculations.

1980-02-20

192

Application of hydro-geochemical simulator to the issues on geological environment  

International Nuclear Information System (INIS)

Recently, it has become clear that the chemical circumstances under which long-term geological evolution occurs must be properly evaluated in order to develop effective remediation programs for contaminated soil, landfills, radioactive waste repositories, and carbon dioxide capture and storage. The issue of acidic leakage from excavated rock stuck was assessed using a hydro-geochemical simulator, TOUGHREACT. We concluded that in order to properly investigate the phenomenon of acidic leakage from excavated pyrite-containing rock stuck, it is important to obtain accurate information about the following factors: intensity of rainfall, unsaturated flow properties of the excavated rock stuck, specific surfaces for oxidation reaction of pyrite, the species and the quantity of other minerals contained in the rock, and secondary minerals produced. (author)

193

Federal Facility Agreement plans and schedules for liquid low-level radioactive waste tank systems at Oak Ridge National Laboratory, Oak Ridge, Tennessee  

Energy Technology Data Exchange (ETDEWEB)

Although the Federal Facility Agreement (FFA) addresses the entire Oak Ridge Reservation, specific requirements are set forth for the liquid low-level radioactive waste (LLLW) storage tanks and their associated piping and equipment, tank systems, at ORNL. The stated objected of the FFA as it relates to these tank systems is to ensure that structural integrity, containment and detection of releases, and source control are maintained pending final remedial action at the site. The FFA requires that leaking LLLW tank systems be immediately removed from service. It also requires the LLLW tank systems that do not meet the design and performance requirements established for secondary containment and leak detection be either upgraded or replaced. The FFA establishes a procedural framework for implementing the environmental laws. For the LLLW tank systems, this framework requires the specified plans and schedules be submitted to EPA and TDEC for ...

1992-03-01

194

FY 1987 current fiscal year work plan  

Energy Technology Data Exchange (ETDEWEB)

This Current Year Work Plan presents a detailed description of the activities to be performed by the Joint Integration Office during FY87. It breaks down the activities into two major work areas: Program Management and Program Analysis. Program Management is performed by the JIO by providing technical planning and guidance for the development of advanced TRU waste management capabilities. This includes equipment/facility design, engineering, construction, and operations. These functions are integrated to allow transition from interim storage to final disposition. JIO tasks include program requirements identification, long-range technical planning, budget development, program planning document preparation, task guidance, task monitoring, information gathering and task reporting to DOE, interfacing with other agencies and DOE lead programs, integrating public involvement with program efforts, and preparation of program status reports for DOE. ...

1986-12-01

195

Estimates of the width of the wetting zone along a fracture subjected to an episodic infiltration event in variably saturated, densely welded tuff  

Energy Technology Data Exchange (ETDEWEB)

A central issue to be addressed within the Nevada Nuclear Waste Storage Investigations (NNWSI) is the role which fractures will play as the variably saturated, fractured rock mass surrounding the waste package responds to heating, cooling, and episodic infiltration events. Understanding the role of fractures during such events will, in part, depend on our ability to make geophysical measurements of perturbations in the moisture distribution in the vicinity of fractures. In this study we first examine the details of the perturbation in the moisture distribution in and around a fracture subjected to an episodic infiltration event, and then integrate that behavior over the scale at which moisture measurements are likely to be made during the Engineered Barrier Design Test of the NNWSI project. To model this system we use the TOUGH hydrothermal code and fracture and matrix properties considered relevant to the welded ash flow ...

1988-05-31

196

Destruction of organic chemicals in Hanford HLW tanks by radiolytic and chemical aging  

International Nuclear Information System (INIS)

The underground storage tanks at the Hanford Complex contain mixed wastes generated over many years from plutonium production and recovery processes. The chemical changes of the organic materials used in the extraction processes and disposed to the tanks have a direct bearing on several specific safety issues, including potential energy releases from these tanks. This paper will give details of a study that is directed towards elucidating thermal and radiological decomposition mechanisms and products of the organic contents of the tanks. The study is being conducted in two parts. The first part, an aging study, will determine kinetics and products of the degradation of a simulated waste subjected to #gamma#-radiation from an external source. Although the simulant will not contain radioactive elements, it will contain other representative inorganic compounds and the primary organic compounds thought to have been disposed to ...

1994-08-21

197

A space crystal diffraction telescope for the energy range of nuclear transitions  

Energy Technology Data Exchange (ETDEWEB)

This paper contains literature from American Power Conference Air Toxics Being Measured Accurately, Controlled Effectively NO{sub x} and SO{sub 2} Emissions Reduced; Surface Condensers Improve Heat Rate; Usable Fuel from Municipal Solid Waste; Cofiring Technology Reduces Gas Turbine Emissions; Trainable, Rugged Microsensor Identifies of Gases; High-Tc Superconductors Fabricated; High-Temperature Superconducting Current Leads; Vitrification of Low-Level Radioactive and Mixed Wastes; Characterization, Demolition, and Disposal of Contaminated Structures; On-Line Plant Diagnostics and Management; Sulfide Ceramic Materials for Improved Batteries; Flywheel Provides Efficient Energy Storage; Battery Systems for Electric Vehicles; Polymer-Electrolyte Fuel Cells for Transportation; Solid-Oxide Fuel Cells for Transportation; Surface Acoustic Wave Sensor Monitors Emissions in Real-Time; Advance Alternative-Fueled Automotive ...

1995-04-01

198

Start of the SAPIERR project of regional final storage of radioactive waste in the European Union; Auftakt des SAPIERR-Projekts ueber eine regionale Endlagerung radioaktiver Abfaelle in der Europaeischen Union  

Energy Technology Data Exchange (ETDEWEB)

The first working meeting of the SAPIERR project about regional final storage of radioactive waste in the European Union was held in Piestany, Slovak Republic, on February 19 and 20, 2004. SAPIERR stands for Support Action: Pilot Initiative for European Regional Repositories. This is an independent study supported financially by the European Union within the 6th Research Framework Program. The background to the project is the debate about the feasibility of regional repositories for radioactive waste in the European Union, which has come up again especially with a view to the new accession countries and the draft of a waste management directive within the framework of the Nuclear Package. The results of the SAPIERR Project will be presented in Brussels at a concluding international seminar, most probably in October 2005. The seminar will be open not only to the participating countries but also to other ...

2004-06-01

199

Less waste corn, more land in soybeans, and the switch to genetically modified crops: trends with important implications to wildlife management  

Science.gov (United States)

An abundance of waste corn, a key food of many wildlife species, has helped make possible the widespread success of wildlife management in the United States over the past half century. We found waste corn post harvest in Nebraska declined by 47% from 1978 to 1998 due primarily to improvements in combine headers resulting in a marked decline in ear loss. The reduction in waste coincided with major declines in fat storage by sandhill cranes and white-fronted geese during spring migration. Sandhill cranes, northern pintails, white-fronted geese, and lesser snow geese avoided soybeans while staging in spring in the Rainwater Basin Area and Central Platte River Valley. These findings and other literature suggest soybeans are a marginal food for wildlife particularly during periods of high energy requirements. Soybean acreage has increased by 600% in the United States since 1950 and now comprises nearly ...

2004-01-01

200

Immobilization of chloride-rich radioactive wastes produced by pyrochemical operations  

Energy Technology Data Exchange (ETDEWEB)

A a result of its former role as a producer of nuclear weapons components, the Rocky Flats Environmental Technology Site (RFETS), Golden, Colorado accumulated a variety of plutonium-contaminated materials. When the level of contamination exceeded a predetermined level (the economic discard limit), the materials were classified as residues rather than waste and were stored for later recovery of the plutonium. Although large quantities of residues were processed, others, primarily those more difficult to process, remain in storage at the site. It is planned for the residues with lower concentrations of plutonium to be disposed of as wastes at an appropriate disposal facility, probably the Waste Isolation Pilot Plant (WIPP). Because the plutonium concentration is too high or because the physical or chemical form would be difficult to get into a form acceptable to WIPP, it may not be possible to dispose of ...

1997-08-01

201

WASTE TREATMENT AND DISPOSAL PROGRESS REPORT FOR JUNE AND JULY 1962  

Science.gov (United States)

9 9 simulated Purex waste oxides was investigated as a function of Na/sub 2/O, CaO and P/sub 2/O/sub 5/ content. All compositions lost some sulfate at 50 to 100 deg C above the softening point. In generai the volatility decreased with increase of either Na/ sub 2/O or CaO relative to P/sub 2/O/sub 5/, but no simple correlation Was indicated. Softening temperatures were lowered by inc ease in Na/sub 2/O vs CaO. Ceramic solids were obtained but no true glasses. Attempts to produce glasses by addition of varying combinations of Al/sub 2/O/sub 3/, PbO, BaO, and B/sub 2/O/ sub 3/ to simulated Pure x waste plus phosphite were unsuccessful. The use of 0.005 M Na/sub 2/C/O/sub 3/ to precipitate calcium from wastes containing up to 3 ppm of phosphate was demonstrated in four pilot plant runs and produced a decrease in the hardness of the waste leaving the clarifier. An inadvertent ...

1962-12-19

202

Engineering study on steam storage power generation. System screening and efficiency  

Energy Technology Data Exchange (ETDEWEB)

Large scale steam storage power generation, one of the new energy storage systems for the future of inflexible electric power sources consisting of nuclear and coal power plants has been studied on the subjects of the systems to be attached to coal and nuclear power units, of the definition of storage efficiency and of the vertical steam storage vessel technology. Steam storage power generation may be hopeful for its higher efficiency similarly defined as of pumped storage plants while high temperature heat storage and the internal structure of large vertical steam storage vessel (accumulator) need to be developed.

1981-11-01

203

Engineering study on steam storage power generation  

International Nuclear Information System (INIS)

Large scale steam storage power generation, one of the new energy storage systems for the future of inflexible electric power sources consisting of nuclear and coal power plants has been studied on the subjects of the systems to be attached to coal and nuclear power units, of the definition of storage efficiency and of the vertical steam storage vessel technology. Steam storage power generation may be hopeful for its higher efficiency similarly defined as of pumped storage plants while high temperature heat storage and the internal structure of large vertical steam storage vessel (accumulator) need to be developed. (author).

1981-01-01

204

Regulatory Framework for Advanced Fuel Cycle Facility Using Pyroprocess in Korea  

International Nuclear Information System (INIS)

Nuclear power plants of 20 units of in Korea are generating about 700 MTU of spent fuels annually. The inventory of spent fuels in Korea were estimated about 10,087.07 MTU at end of 2008, and the storage space of spent fuels won't be available any more at 2016 due to the saturation of the spent fuel pools in the plants. In addition, in order to reduce carbon emission and correspond to the enormous electricity demand in Korea, 8 units of nuclear power plants are under construction and several more plants are under planning. The 100,000 MTU of spent fuel inventory are expected by the year of 2095 in Korea. Therefore, short term and long term of spent fuel management plans are under discussion and implementation in Korea. As a short term of spent fuel management strategy for the target year of 2016, central or local spent fuel dry interim storage options are mostly under discussion. As a long term of management plan, fast reactor and advanced fuel ...

2010-10-01

205

Determination of radon-222 concentration in inside environments of the Instituto de Engenharia Nuclear, Brazil; Determinacao da concentracao de radonio-222 nos ambientes internos das instalacoes do Instituto de Engenharia Nuclear  

Energy Technology Data Exchange (ETDEWEB)

The gotten concentrations of radon-222 in the installations of the IEN had been determined using the active and passive methods. The active method consisted on the use of the alpha spectrometry with a portable equipment Tracerlab Instruments WLM- Plus. In the determination for the passive method, one used detectors of nuclear strokes of type LEXAN. The raised values had been gotten in the wastes deposit and its annexes, room of the press and laboratory of wastes handling. It was observed, in this sector, an instantaneous measure of alpha spectrometry, concentrations around 1000 Bq.m-3, which had over all to the function of storage, the sector, a great volume of natural radioactive materials, especially of radium-226. This determination was carried through in an extreme situation of ventilation zero, where the gates had been kept closed during the execution of the same one. It was observed, however, a considerable fall, with ...

2000-07-01

206

Characterization of trace elements and radionuclides and their risk assessment in red mud  

International Nuclear Information System (INIS)

Red mud is a waste and tail material from primary aluminum production, and is named for its color, coming from its iron oxide content. The quantity of red mud is almost equal to the primary aluminum production and leads to a considerable environmental issue. Red mud of the ETI Seydisehir Aluminum Plant is considered as detrimental waste for storage due to its content of various metal oxides, elements and caustics. This detrimental effect is classified into two groups: first, environmental health and second, the cost of storage. In order to minimize the negative effect of red mud, there have been or are presently many investigations carried out on usage of red mud in building materials. However, no effective way of utilizing red mud has yet been found. In this study domestic red mud was investigated and chemical analyses were performed by EDAX and XRF techniques. Radioactivity of the samples was also ...

2008-04-01

207

Long-term storage of solar heat  

Energy Technology Data Exchange (ETDEWEB)

Stochastic models for the simulation of global radiation are discussed. Thermal transients in the ground are analyzed. The performance of buried-pipe storage and a space heating system with long-term storage is described.

1981-06-01

208

Probabilistic safety analysis of transportation of spent fuel  

International Nuclear Information System (INIS)

The report presents the results of the study carried out to estimate the accident risk involved in the transport of spent fuel from Rajasthan Atomic Power Station near Kota to the fuel reprocessing plant at Tarapur. The technique of probabilistic safety analysis is used. The fuel considered is the Indian pressurised heavy water reactor fuel with a minimum cooling period of 485 days. The spent fuel is transported in a cuboidal, naturally-cooled shipping cask over a distance of 822 km by rail. The Indian rail accident statistics are used to estimate the basic rail accident frequency. The possible ways in which a release of radioactive material can occur from the spent fuel cask are identified by the fault tree analysis technique. The release sequences identified are classified into eight accident severity categories, and release fractions are assigned to each. The consequences resulting from the release are estimated by the computer code RADTRAN ...

1977-09-05

209

Mechanical properties of an as-cast heavy-sectioned ferritic spheroidal graphite cast iron  

Energy Technology Data Exchange (ETDEWEB)

In the production of heavy-sectioned ferritic spheroidal graphite iron castings for such parts as spent fuel shipping container (cask), undesirable structures like abnormal graphite lamella, pearlite or so-called chinese script type of inclusions tend to appear, deteriorating the mechanical properties at the central part of the section where molten iron freezes last. 500 mm thick cylindrical vessels with bottom, weighing 18 tons and 33 tons, were poured as trial products of casks. Solidification structure and mechanical properties were examined at many portions of the castings. By controlling chemical composition, solidification time and inoculation process the structure and the mechanical properties in the last portion of the section to solidify were improved. Sufficiently homogeneous heavy-sectioned ferritic spheroidal graphite iron castings were successfully produced in the as-cast state. In addition, quality assurance process by using test ...

1987-11-01

210

Immobilization of waste material  

International Nuclear Information System (INIS)

A method is described for immobilizing or solidifying waste material, which includes blending the waste material with powdered metal and subjecting the mixture of waste material and powdered metal to high pressure. (author).

211

DISPOSING DEVICE FOR WASTE  

J-STORE (Japan)

Full Text Available

2005-12-19

212

Natural convection cooling of circumferentially finned transport casks  

International Nuclear Information System (INIS)

It may be stated that for the calculation of the heat transfer coefficients for natural convection cooling of large-diameter finned surfaces it is necessary to take in consideration the effects of the fin length, fin material and of the azimuthal angle around the cylinder. The present results replace earlier less accurate correlations gained from the same measurements. The new, better correlation was elaborated with the aid of the improved method of evaluation of multiple parameters of a measurement matrix of multiple dimension (one dimension for each parameter), rendering the sum of the squares error a minimum at the same time for the complete matrix. 5 references.

1983-12-01

213

The protein storage vacuole  

UK PubMed Central (United Kingdom)

Storage proteins are deposited into protein storage vacuoles (PSVs) during plant seed development and maturation and stably accumulate to high levels; subsequently, during germination the storage...Full Text Available

2001-12-10

217

Floating systems - Atkins  

Wastenet

...Floating systems - Atkins storage and offloading units (FPSOs). ...

220

The effects of organosulfur compounds upon the storage stability of Jet A fuel  

Science.gov (United States)

This study examined the effect of sulfur-containing compounds on the storage stability of Jet A

1981-01-01

221

Safe Type of Transference for Spent Fuel  

International Science & Technology Center (ISTC)

Safe Transference of Spent Fuel Assemblies from Near-Reactor Storage Pools to Long-term "Dry" Storage

222

Fuel Assembly Materials under Dry Storage  

International Science & Technology Center (ISTC)

Behavior of Nuclear Reactor Fuel Assembly Materials during Their Long-Term Dry Storage

223

The application of computer modeling to health effect research  

Energy Technology Data Exchange (ETDEWEB)

In the United States, estimates show that more than 30,000 hazardous waste disposal sites exist, not including military installations, U.S. Department of Energy nuclear facilities, and hundreds and thousands of underground fuel storage tanks; these sites undoubtedly have their own respective hazardous waste chemical problems. When so many sites contain hazardous chemicals, how does one study the health effects of the chemicals at these sites? There could be many different answers, but none would be perfect. For an area as complex and difficult as the study of chemical mixtures associated with hazardous waste disposal sites, there are no perfect approaches and protocols. Human exposure to chemicals, be it environmental or occupational, is rarely, if ever, limited to a single chemical. Therefore, it is essential that we consider multiple chemical effects and interactions in our risk assessment process. ...

1996-12-31

224

Synthesis, structural characterization, and performance evaluation of resorcinol-formaldehyde (R-F) ion-exchange resin  

International Nuclear Information System (INIS)

The 177 underground storage tanks at the DOE's Hanford Site contain an estimated 180 million tons of high-level radioactive wastes. It is desirable to remove and concentrate the highly radioactive fraction of the tank wastes for vitrification. Resorcinol-formaldehyde (R-F) resin, an organic ion-exchange resin with high selectivity and capacity for the cesium ion, which is a candidate ion-exchange material for use in remediation of tank wastes. The report includes information on the structure/function analysis of R-F resin and the synthetic factors that affect performance of the resin. CS-100, a commercially available phenol-formaldehyde (P-F) resin, and currently the baseline ion-exchanger for removal of cesium ion at Hanford, is compared with the R-F resin. The primary structural unit of the R-F resin was determined to consist of a 1,2,3,4-tetrasubstituted resorcinol ring unit while CS-100, was ...

2004-09-10

225

Evaluation of methods to measure surface level in waste storage tanks: Second test sequence  

Energy Technology Data Exchange (ETDEWEB)

This report describes the results of a program conducted at the Pacific Northwest Laboratory (PNL) and Westinghouse Hanford Company (WHC) to identify alternative methods to measure the surface level in the waste tanks. This program examined commercially available devices for measuring the distance to a target. This is a continuation of a program started in FY93. In the first test sequence, tests were performed.on five devices to determine their applicability to measure the surface level in the waste tanks. The devices were the Enraf-Nonius{trademark} Model 872 Radar Gauge, the Enraf-Nonius{trademark} Model 854 Advanced Technology Gauge (ATG), the Stanley Tool Laser Measuring Device, the Robertshaw Inven-Tel{reg_sign} Precision Level Gauge, and the Micro Switch Model 942 Acoustic Sensor. In addition, discussions were held with several manufacturer representatives regarding other potential devices. The results of these tests were documented in a ...

1993-09-01

226

A desiccant dehumidifier for electric vehicle heating  

Energy Technology Data Exchange (ETDEWEB)

Vehicle heating requires a substantial amount of energy. Engines in conventional cars produce enough waste heat to provide comfort heating and defogging/defrosting, even under very extreme conditions. Electric vehicles (EVs), however, generate little waste heat. Using battery energy for heating may consume a substantial fraction of the energy storage capacity, reducing the vehicle range, which is one of the most important parameters in determining EV acceptability. Water vapor generated by the vehicle passengers is in large part responsible for the high heating loads existing in vehicles. In cold climates, the generation of water vapor inside the car may result in water condensation on the windows, diminishing visibility. Two strategies are commonly used to avoid condensation on windows: windows are kept warm, and a large amount of ambient air is introduced in the vehicle. Either strategy results in a substantial heating ...

1996-09-01

227

European Commission - Environment  

Wastenet

...Species - see CITES Trade of Dangerous Chemicals Transport and Environment U Urban Environment Use of natural resources V Volatile Organic Compounds W Waste Landfills Waste electrical and electronic equipment - see WEEE Waste incineration Waste legislation - reporting Waste management planning Waste oils Waste shipments Waste water - see Urban waste water Water Bathing Water Drinking water Floods Marine environment Urban waste water Water Framework Directive WEEE - Waste Electric and Electronic Equipment Wildlife ...

228

Subsurface Injection of Liquid Waste  

Science.gov (United States)

... Other Sources Toxics Intranet Subsurface Injection of Liquid Waste -- Florida Surface features of a typical...

230

Radiation protection and the management of radioactive waste in the oil and gas industry  

CERN Document Server

Radiation protection and the management of radioactive waste in the oil and gas industry

2003-01-01

232

On-site burning, remote camp  

Science.gov (United States)

... wood, kitchen wastes, and human faeces. The ash from such waste burning shall be deposited and ...

233

Liquid Radioactive Wastes Processing  

International Science & Technology Center (ISTC)

Methods of Decontamination, Utilization, and Deactivation of Liquid Radioactive Wastes

234

IEE, accelerated waste mgt, McM  

Science.gov (United States)

... in ATCM Recommendation XIV-2. The USAP's materials and waste management efforts are consistent with ...

235

Human Waste Handling-Kooyman  

Science.gov (United States)

... wood, kitchen wastes, and human faeces with the ash from such burning deposited and retained in an ...

236

Dioxins in the Baltic sea  

Wastenet

for municipal waste iron ore sinter plants incinerators for clinical waste facilities of the non-ferrous metal

237

Combustion of Crop Production Wastes  

International Science & Technology Center (ISTC)

Development, Investigation and Improvement of a System of Incinerating Crop Production Wastes in Small Capacity Boilers

239

Transuranic contaminated waste form characterization and data base  

Energy Technology Data Exchange (ETDEWEB)

This volume contains 5 appendices. Title listing are: technologies for recovery of transuranics; nondestructive assay of TRU contaminated wastes; miscellaneous waste characteristics; acceptance criteria for TRU waste; and TRU waste treatment technologies.

1980-07-01

240

Process Waste Assessment for inorganic solid waste and empty containers <30 gallons  

Energy Technology Data Exchange (ETDEWEB)

This Process Waste Assessment was conducted to evaluate the two largest hazardous waste streams generated on-site at Sandia National Laboratory (SNL)/California -- ``Other Inorganic Solid Waste`` and ``Empty Containers <30 Gallons.``

1993-12-01

241

LAW ON WASTE MANAGEMENT  

Wastenet

1 to the operator of a waste collective system by an agreement or contract. The conditions for the ...Fees of the waste collective system are subject to the supervision of the authority responsible for market surveillance. ...The operator of waste collection system collects wastes from producers and holder and transports these to a collection

242

Waste management units - Savannah River Site. Volume 1, Waste management unit worksheets  

Energy Technology Data Exchange (ETDEWEB)

This report is a compilation of worksheets from the waste management units of Savannah River Plant. Information is presented on the following: Solid Waste Management Units having received hazardous waste or hazardous constituents with a known release to the environment; Solid Waste Management Units having received hazardous waste or hazardous constituents with no known release to the environment; Solid Waste Management Units having received no hazardous waste or hazardous constituents; Waste Management Units having received source; and special nuclear, or byproduct material only.

1989-10-01

243

Challenges for Lithuania: Ignalina NPP Early Closure  

International Nuclear Information System (INIS)

As a condition of accession into the European Union (EU), Lithuania is committed to the closure and decommissioning of Ignalina NPP comprising two RBMK-1500 reactor units (Fig. 1). It was agreed in a special protocol to the Accession Treaty that, in return for adequate EU financial assistance, Unit 1 would be closed before 2005 and Unit 2 by the end of 2009. The first unit was duly shut down on December 31, 2004. Lithuania, which has borders with Russia (Kaliningrad territory), Poland, Latvia and Belarus, spent fifty years as part of the Soviet Union and was deeply integrated into its economy and electrical infrastructure. At the break-up of the USSR, Lithuania inherited electricity generating capacity designed to supply the north-west region including ownership of Ignalina NPP located in the north-east of the country. Ignalina NPP Unit 1 was commissioned in 1983, Unit 2 in 1987; the planned lifespan of each unit was 30 years. Construction of a third unit was started but never ...

2008-01-01

244

High-tech hydro: an overview of pumped storage  

Science.gov (United States)

A growing number of pumped storage plants installed within the US brings attention to the increasing significance of pumped storage as a source of electrical generation capacity. Because of the special benefits this technology has to offer, hydroelectric pumped storage is an option that many utilities should consider for the supply of new capacity requirements. This article surveys the development and use of pumped storage in the US, and considers the potential for the future development of this technology. Although some of the problems that have occurred on recent projects highlight the role of pumped storage as a technological proving ground, the article puts forth the view that pumped storage is maturing to play a significant role in US electricity supply.

245

Wetlands - A valuable resource for the '90s  

Energy Technology Data Exchange (ETDEWEB)

The nation's wetlands are a valuable resource serving many important natural, industrial, commercial and recreational functions. Wetlands protect shore areas from waves and storms; act as storage areas for flood waters; remove waste from water by trapping soils or silt which settle to the bottom; improve water quality and reduce pollution; are a commercial breeding ground for fish and other foods; and provide space for recreation and habitat for wildlife. They also are located in prime industrial development areas. Recent wetlands losses have caused much public outcry, politicking and regulatory efforts to prevent this trend. During the '90s, the public will see efforts to strike a proper balance regarding wetlands use. Today, wetlands protection is a permitting issue for nearly every major industrial or commercial development and expansion project. Wetlands permit requirements affect a range of business entities. Any project ...

1993-04-15

246

Study of iodine migration in zirconia using stable and radioactive ion implantation  

Energy Technology Data Exchange (ETDEWEB)

The large uranium fission cross section leading to iodine and the behaviour of this element in the cladding tube during energy production and afterwards during waste storage is a crucial problem, especially for {sup 129}I which is a very long half-life isotope (T=1.59 x 10{sup 7} yr). Since a combined external and internal oxidation of the zircaloy cladding tube occurs during the reactor processing, iodine diffusion parameters in zirconia are needed. In order to obtain these data, stable iodine atoms were first introduced by ion implantation into zirconia with an energy of 200 keV and a dose equal to 8 x 10{sup 15} at cm{sup -2}. Diffusion profiles were measured using 3 MeV alpha-particle Rutherford backscattering spectrometry at each step of the annealing procedure between 700 C and 900 C. In such experiments a reduced iodine concentration was observed, which correlated to a diffusion-like process. Similar analysis has been performed using ...

1998-03-01

247

Environmental fate and distribution of technetium-99 in a deciduous forest ecosystem  

International Nuclear Information System (INIS)

The uptake of "9"9Tc by trees intercepting contaminated groundwater from a radioactive waste storage site was measured to identify the major "9"9Tc pools within the woodland ecosystem and to assess the relative mobility of "9"9Tc in the existing element cycle. The highest average "9"9Tc concentrations in vegetation were found in herbaceous plants. Tree wood was the major above-ground pool for "9"9Tc because of the high concentrations in wood as well as the large amount of wood relative to other biomass at the site. Technetium was not easily leached from the trees by rainfall and was not readily extractable from forest floor leaf litter by water. The relative importance of return pathways for "9"9Tc to the forest floor was leaf fall > stemflow > throughfall, indicating that "9"9Tc was conserved by the trees. Snails and millipedes from the leaf litter layer concentrated technetium 20- and 16-fold, respectively, above levels found in the ...

248

Characterization of spent fuel approved testing material: ATM-106  

Energy Technology Data Exchange (ETDEWEB)

The characterization data obtained to date are described for Approved Testing Material (ATM)-106 spent fuel from Assembly BT03 of pressurized-water reactor Calvert Cliffs No. 1. This report is one in a series being prepared by the Materials Characterization Center at Pacific Northwest Laboratory on spent fuel ATMs. The ATMs are receiving extensive examinations to provide a source of well- characterized spent fuel for testing in the US Department of Energy Office of Civilian Radioactive Waste Management (OCWRM) program. ATM-106 consists of 20 full-length irradiated fuel rods with rod-average burnups of about 3700 GJ/kgM (43 MWd/kgM) and expected fission gas release of /approximately/10%. Characterization data include (1) as-fabricated fuel design, irradiation history, and subsequent storage and handling; (2) isotopic gamma scans; (3) fission gas analyses; (4) ceramography of the fuel and metallography of the cladding; (5) calculated nuclide ...

1988-10-01

249

Characterization of spent fuel approved testing material: ATM-103  

Energy Technology Data Exchange (ETDEWEB)

The characterization data obtained to date are described for Approved Testing Material (ATM)-103, which is spent fuel from Assembly D101 of pressurized-water reactor Calvert Cliffs, No. 1. This report is one in a series being written by the Materials Characterization Center (MCC) at Pacific Northwest Laboratory (PNL) on spent fuel ATMs. The ATMs are receiving extensive examinations to provide a source of well-characterized spent fuel for testing in the US nuclear waste repository program. ATM-103 consists of 176 full-length irradiated fuel rods with rod-average burnups of about 2600 GJ/kgM (30 MWd/kgM) and less than 1% fission gas release. Characterization data include 1) as-fabricated fuel design, irradiation history, and subsequent storage and handling; 2) isotopic gamma scans; 3) fission gas analyses; 4) ceramography of the fuel and metallography of the cladding; 5) special fuels studies involving analytical transmission electron microscopy ...

1988-04-01

250

Characterization of spent fuel approved testing material--ATM-104  

Energy Technology Data Exchange (ETDEWEB)

The characterization data obtained to date are described for Approved Testing Material 104 (ATM-104), which is spent fuel from Assembly DO47 of the Calvert Cliffs Nuclear Power Plant (Unit 1), a pressurized-water reactor. This report is one in a series being prepared by the Materials Characterization Center at Pacific Northwest Laboratory (PNL) on spent fuel ATMs. The ATMs are receiving extensive examinations to provide a source of well-characterized spent fuel for testing in the US Department of Energy Office of Civilian Radioactive Waste Management (OCRWM) Program. ATM-104 consists of 128 full-length irradiated fuel rods with rod-average burnups of about 42 MWd/kgM and expected fission gas release of about 1%. A variety of analyses were performed to investigate cladding characteristics, radionuclide inventory, and redistribution of fission products. Characterization data include (1) fabricated fuel design, irradiation history, and subsequent ...

1991-12-01

251

Characterization of spent fuel approved testing material---ATM-105  

Energy Technology Data Exchange (ETDEWEB)

The characterization data obtained to data are described for Approved Testing Material 105 (ATM-105), which is spent fuel from Bundles CZ346 and CZ348 of the Cooper Nuclear Power Plant, a boiling-water reactor. This report is one in a series being prepared by the Materials Characterization Center at Pacific Northwest Laboratory (PNL) on spent fuel ATMs. The ATMs are receiving extensive examinations to provide a source of well-characterized spent fuel for testing in the US Department of Energy Office of Civilian Radioactive Waste Management (OCRWM) Program. ATM-105 consists of 88 full-length irradiated fuel rods with rod-average burnups of about 2400 GJ/kgM (28 MWd/kgM) and expected fission gas release of about 1%. Characterization data include (1) descriptions of as-fabricated fuel design, irradiation history, and subsequent storage and handling; (2) isotopic gamma scans; (3) fission gas analyses; (4) ceramography of the fuel and metallography ...

1991-12-01

252

Uranium and thorium based phosphate matrix: synthesis, characterizations and lixiviation; Matrices a base de phosphate d'uranium et de thorium: syntheses, caracterisations et lixiviation  

Energy Technology Data Exchange (ETDEWEB)

In the framework of the search for a ceramic material usable in the radioactive waste storage, uranium and thorium phosphates have been investigated. Their experimental synthesis conditions have been entirely reviewed, they lead to the preparation of four new compounds: U(UO{sub 2})(PO{sub 4}){sub 2}, U{sub 2}O(PO{sub 4}){sub 2}, UCIPO{sub 4}, 4H{sub 2}O, and Th{sub 4}(PO{sub 4}){sub 4}P{sub 2}O{sub 7}. Experimental evidenced are advanced for non existent compounds such as: U{sub 3}(PO{sub 4}){sub 4}, U{sub 2}O{sub 3}P{sub 2}O{sub 7} and Th{sub 3} (PO{sub 4}){sub 4}. Characterization by several techniques (X-rays and neutron powder diffractions, UV-Visible and Infra-red spectroscopies, XPS,...) were performed. The ab initio structure determination of U(UO{sub 2})(PO{sub 4}){sub 2} has been achieved by X-rays and refined by neutron diffractions. Through its physico-chemical analysis, we found that this compound was a new mixed valence uranium ...

1995-03-01

253

Investigation of Nuclide Importance to Functional Requirements Related to Transport and Long-Term Storage of LWR Spent Fuel  

Energy Technology Data Exchange (ETDEWEB)

The radionuclide characteristics of light-water-reactor (LWR) spent fuel play key roles in the design and licensing activities for radioactive waste transportation systems, interim storage facilities, and the final repository site. Several areas of analysis require detailed information concerning the time-dependent behavior of radioactive nuclides including (1) neutron/gamma-ray sources for shielding studies, (2) fissile/absorber concentrations for criticality safety determinations, (3) residual decay heat predictions for thermal considerations, and (4) curie and/or radiological toxicity levels for materials assumed to be released into the ground/environment after long periods of time. The crucial nature of the radionuclide predictions over both short and long periods of time has resulted in an increased emphasis on thorough validation for radionuclide generation/depletion codes. Current radionuclide generation/depletion codes have the ...

1995-01-01

254

Stationary low power reactor No. 1 (SL-1) accident site decontamination & dismantlement project  

Science.gov (United States)

The Army Reactor Area (ARA) II was constructed in the late 1950s as a test site for the Stationary Low Power Reactor No. 1 (SL-1). The SL-1 was a prototype power and heat source developed for use at remote military bases using a direct cycle, boiling water, natural circulation reactor designed to operate at a thermal power of 3,000 kW. The ARA II compound encompassed 3 acres and was comprised of (a) the SL-1 Reactor Building, (b) eight support facilities, (c) 50,000-gallon raw water storage tank, (d) electrical substation, (e) aboveground 1,400-gallon heating oil tank, (f) underground 1,000-gallon hazardous waste storage tank, and (g) belowground power, sewer, and water systems. The reactor building was a cylindrical, aboveground facility, 39 ft in diameter and 48 ft high. The lower portion of the building contained the reactor pressure vessel surrounded by gravel shielding. Above the pressure vessel, in the center portion ...

1995-11-01

255

Gas fired heaters and ventilation system improve indoor air quality and thermal comfort  

Energy Technology Data Exchange (ETDEWEB)

Rotex Inc. has designed and manufactured industrial sifting equipment since 1844. This site (an existing industrial facility) encompasses approximately 140,000 ft[sup 2] (13,006 m[sup 2]) of offices, R D shops, assembly and storage areas, as well as a large welding shop that was the main focus of this project. This facility consists of three separate buildings that are all connected and open to one another. The original building dates from 1908. The newest addition (32,400 ft[sup 2]; 3,010 m[sup 2]) was added in 1977, and is referred to as the 77 Building. This building was initially equipped with oil fired heating equipment due to the moratorium on new gas sales that was in effect at that time. This project was driven by the client's need to remove underground oil storage tanks to comply with environmental standards. This article describes the 77 Building conversion from oil to an environmentally cleaner fuel, natural gas. Existing ...

1994-03-01

256

Determination of the helium diffusion coefficient in nuclear waste storage ceramics by a nuclear reaction analysis method  

International Nuclear Information System (INIS)

Host matrices for actinide immobilisation will undergo the formation of large helium quantities due to alpha decay. Helium diffusion rate has to be known in order to predict the long-term behaviour of the material, and particularly, the influence of helium accumulation on mechanical properties. A nuclear reaction analysis method, namely the "3He(d, p)"4He reaction, has been used to analyse the evolution of "3He profiles after ion implantations at 1 and 3 MeV in two materials, monoclinic ZrO_2 (as a test material) and Ca_9Nd(PO_4)_5(SiO_4)F_1_._5(OH)_0_._5 britholite (envisaged for Am and Pu long-term storage). Two data processing methods are used: the classical excitation curve (proton yields versus deuteron energy) and second, the proton energy spectrum for a given deuteron energy. The characteristics of the "3He profiles (depth, width) obtained by both methods are compared to SRIM estimations. Their evolution during subsequent annealings allows an estimation of ...

2002-06-01

257

Basic aspects of the concept of reactor compartment (including damaged compartments) management during utilization of nuclear powered submarines -- High priority R and D  

International Nuclear Information System (INIS)

Large-scale decommissioning of Russian nuclear-powered submarines (NPS) and their utilization prospects gave rise to numerous complicated scientific and technical, as well as economic, problems. Problems of handling of radioactive equipment from the reactor compartments (RC) are among the vital ones, arousing a growing concern with the public. Without solution of the problems the processes of NPS utilization can not be considered completed. It involves potential hazard, for the environment both from NPS being paid up (temporal on-float storage) with unloaded spent nuclear fuel (SNF), and RC, cut from submarine hull, containing highly radioactive equipment and materials but no SNF. Diverse variations of the concept of reactor compartment handling of NPS subject to, utilization are possible, but, in principle, there are essentially two variants: (1) RC utilization directly in the course of NPS utilization, envisaging removal of radioactive equipment from the reactor ...

1996-03-10

258

The state of energy storage in electric utility systems and its effect on renewable energy resources  

Energy Technology Data Exchange (ETDEWEB)

This report describes the state of the art of electric energy storage technologies and discusses how adding intermittent renewable energy technologies (IRETs) to a utility network affects the benefits from storage dispatch. Load leveling was the mode of storage dispatch examined in the study. However, the report recommended that other modes be examined in the future for kilowatt and kilowatt-hour optimization of storage. The motivation to install storage with IRET generation can arise from two considerations: reliability and enhancement of the value of energy. Because adding storage increases cost, reliability-related storage is attractive only if the accruing benefits exceed the cost of storage installation. The study revealed that the operation of storage should not be guided by the output of the ...

1994-08-01

259

200 Area Interim Storage Area Technical Safety Requirements  

Energy Technology Data Exchange (ETDEWEB)

The 200 Area Interim Storage Area Technical Safety Requirements define administrative controls and design features required to ensure safe operation during receipt and storage of canisters containing spent nuclear fuel. This document is based on the 200 Area Interim Storage Area, Annex D, Final Safety Analysis Report which contains information specific to the 200 Area Interim Storage Area.

2000-03-15

260

Waste management at Los Alamos: Protecting our environment  

Energy Technology Data Exchange (ETDEWEB)

This report consists of a broad overview of activities at Los Alamos National Laboratory (LANL). The following topics are discussed: The growth of the waste management group; what we do today; the mission of the waste management group; the liquid waste treatment section; the radioactive liquid waste project office; the chemical waste section; the radioactive waste section; and the technical support section.

1993-11-01

261

Radioactive waste  

Energy Technology Data Exchange (ETDEWEB)

The paper deals with the disposal of radioactive waste and the plans for dealing with solid wastes of intermediate and low levels of activity, which are the responsibility of NIREX. NIREX is an executive body which co-ordinates the waste-disposal plans of the main radioactive waste producers. The disposal routes for the active wastes are described including the deep disposal of wastes containing material that will remain active for thousands of years. Requirements for deep burial are outlined with reference to the geology and hydrogeology of the site. Monitoring, maintenance and surveillance are mentioned for the protection of the public.

1984-02-01

262

The Decommissioning of the Trino Nuclear Power Plant  

Energy Technology Data Exchange (ETDEWEB)

Following a referendum in Italy in 1987, the four Nuclear Power Plants (NPPs) owned and operated by the state utility ENEL were closed. After closing the NPPs, ENEL selected a ''safestore'' decommissioning strategy; anticipating a safestore period of some 40-50 years. This approach was consistent with the funds collected during plant operation, and was reinforced by the lack of both a waste repository and a set of national free release limits for contaminated materials in Italy. During 1999, twin decisions were made to privatize ENEL and to transform the nuclear division into a separate subsidiary of the ENEL group. This group was renamed Sogin and during the following year, ownership of the company was transferred to the Italian Treasury. On formation, Sogin was asked by the Italian government to review the national decommissioning strategy. The objective of the review was to move from a safestore strategy to a prompt ...

2002-02-27

263

Quarterly progress report for the Chemical and Energy Research Section of the Chemical Technology Division: October-December 1997  

Energy Technology Data Exchange (ETDEWEB)

This report summarizes the major activities conducted in the Chemical and Energy Research Section of the Chemical Technology Division at Oak Ridge National Laboratory (ORNL) during the period October--December 1997. The section conducts basic and applied research and development in chemical engineering, applied chemistry, and bioprocessing, with an emphasis on energy-driven technologies and advanced chemical separations for nuclear and waste applications. The report describes the various tasks performed within six major areas of research: Hot Cell Operations, Process Chemistry and Thermodynamics, Separations and Materials Synthesis, Fluid Structure and Properties, Biotechnology Research, and Molecular Studies. The name of a technical contact is included with each task described, and readers are encouraged to contact these individuals if they need additional information. Activities conducted within the area of Hot Cell Operations included efforts to optimize the ...

1999-02-01

264

Natural radiation exposure occurring at handling, storage and disposal of natural radioactive materials; Strahlenbelastung bei Umgang, Lagerung und Abfallhaltung von natuerlicher Radioaktivitaet in Rohstoffen  

Energy Technology Data Exchange (ETDEWEB)

Processing certain raw materials containing natural radioactive isotopes (e.g. U-238, Th-232 or K- 40) into products such as glas, abrasives, grinding materials or electrodes used for gasshielded tungsten-arc welding also leads to certain concentrations of industrial waste containing natural radioactive materials. Such industrial waste does not necessarily contain natural radioactive substances in concentrations exceeding the highest possible levels but nevertheless in significantly measurable quantities. This, however, frequently leads to confusion bordering on irritation by entities processing such substances as well as the general public, since they tend to believe natural radioactive substances in unobjectable concentration to cause similar or identical - health - consequences as man made radioactive substances in detrimental concentration. Radioactive materials may be incorporated intentionally or unintentionally into the product as main ...

2009-07-01

265

Natural radiation exposure occurring at handling, storage and disposal of natural radioactive materials  

International Nuclear Information System (INIS)

Processing certain raw materials containing natural radioactive isotopes (e.g. U-238, Th-232 or K- 40) into products such as glas, abrasives, grinding materials or electrodes used for gasshielded tungsten-arc welding also leads to certain concentrations of industrial waste containing natural radioactive materials. Such industrial waste does not necessarily contain natural radioactive substances in concentrations exceeding the highest possible levels but nevertheless in significantly measurable quantities. This, however, frequently leads to confusion bordering on irritation by entities processing such substances as well as the general public, since they tend to believe natural radioactive substances in unobjectable concentration to cause similar or identical - health - consequences as man made radioactive substances in detrimental concentration. Radioactive materials may be incorporated intentionally or unintentionally into the product as main ...

2009-09-21

266

Medical consequences of radiation accidents  

International Nuclear Information System (INIS)

Since 1945, more than 1.8 x 10"2"1 Bq of artificial radionuclides have been released into the atmosphere. Approximately 2.04 x 10"1"8B, i.e. approx. 0.11%, are the result of accidents at nuclear industrial facilities. This percentage is causing increased interest among researchers. This is due to the fact that in the wake of accidental release radionuclides become distributed unevenly across the Earth's surface, and the associated exposures, fluctuating from background level to several grays, an induce both stochastic and deterministic effects in the irradiated population. A comparative analysis of the medical consequences of the twentieth century's most serious nuclear events, namely the authorized dumping of high level radioactive waste into the river Techa in 1950, the explosion of a storage tank containing long lived radioactive waste in the Southern Urals in 1957, the fire at Sellafield in 1957 and the accident at the ...

1995-10-01

267

FY 1986 current fiscal year work plan  

Energy Technology Data Exchange (ETDEWEB)

This Current Year Work Plan presents in detail a description of the activities to be performed by the Joint Integration Office/RI during FY86. It breaks down the activities into two major work areas: Program Management and Program Analysis. Program Management is performed by the JIO/RI by providing technical planning and guidance for the development of advanced TRU waste management capabilities. This includes equipment/facility design, engineering, construction, and operations. These functions are integrated to allow transition from interim storage to final disposition. JIO/RI tasks include program requirements identification, long-range technical planning, budget development, program planning document preparation, task guidance development, task monitoring, task progress information gathering and reporting to DOE, interfacing with other agencies and DOE lead programs, integrating public involvement with program efforts, and preparation of ...

1985-11-01

268

Regional assessment of nonforestry related biomass resources: Virginia  

Energy Technology Data Exchange (ETDEWEB)

This document is a collection of spreadsheets detailing on a county by county basis the agricultural crop, agricultural wastes, municipal wastes, and industrial wastes of Virginia that are potential biomass energy sources.

1988-11-01

269

Regional assessment of nonforestry related biomass resources: Florida  

Energy Technology Data Exchange (ETDEWEB)

This document is a collection of spreadsheets detailing in a county by county manner the agricultural crop, agricultural wastes, municipal wastes and industrial wastes in Florida that are potential biomass energy sources.

1988-11-01

270

Regional assessment of nonforestry related biomass resources: Alabama  

Energy Technology Data Exchange (ETDEWEB)

This document is a collection of spreadsheets detailing on a county by county basis the agricultural crop, agricultural wastes, municipal wastes and industrial wastes of Alabama that are potential biomass energy sources.

1988-11-01

271

Department of the  

Wastenet

Waste Technology and Innovation Study Final Report ...Waste Technology and Innovation Study Final Report 21/18569/150554 ...Survey of waste and resource recovery related technology and innovation, including products and product uses

272

Addressing the Question of the Effect of RBC Storage on Clinical Outcomes: The Red Cell Storage Duration Study (RECESS) (Section 7)  

UK PubMed Central (United Kingdom)

The question of whether storage of red blood cells (RBCs) alters their capacity to deliver oxygen and affects patient outcomes remains in a state of clinical equipoise. Studies of the changes...Full Text Available

2010-08-01

273

Transportation for reprocessing of the spent nuclear fuel (SNF) of TVR ITEP research reactor and proposals for SNF management plans for the RA reactor  

International Nuclear Information System (INIS)

The TVR heavy water research reactor was deployed at Moscow Institute of Theoretical and Experimental Physics. In 1990, the final batch of the spent nuclear fuel from this reactor was shipped to Production Association (PA) 'Mayak' for reprocessing. The SNF removal was a stage of the reactor decommissioning activities. The designs of the TVR reactor and its fuel elements are similar to the RA reactor designs. Two ways of the RA reactor SNF transportation to PA 'Mayak' have been considered: in aluminum barrels and in additional canisters using respectively TUK-32 and TUK-19 shipping casks. The practical experience and the equipment used to prepare for the TVR reactor SNF removal can be helpful to the RA reactor personnel in finding the best way to perform these engineering operations. (author)

2003-03-09

274

Proposed subcritical measurements for fresh and spent highly enriched plate type fuel assemblies  

Energy Technology Data Exchange (ETDEWEB)

A collaborative experimental research program has been established between industry and university partners to evaluate the subcritical behavior of fresh and spent highly enriched fuel assemblies at the University of Missouri Research Reactor (MURR). This proposed program will involve a series of subcritical measurements using the Oak Ridge National Laboratory (ORNL) developed {sup 252}Cf source-driven noise technique. Measurements evaluating the subcritical behavior of simple arrays of fresh MURR assemblies will be performed for evaluating the spectral effects of materials typically found in shipping casks such as lead, steel, aluminum, and boron. Also, measurements will be performed on spent assemblies to characterize physics parameters which may be useful in determining the subcritical behavior of fuels for reactivity credit of actinide burnup and fission product poisoning.

1997-09-01

275

Low temperature latent heat thermal energy storage - heat storage materials  

Energy Technology Data Exchange (ETDEWEB)

Heat-of-fusion storage materials for low temperature latent heat storage in the temperature range 0-120 C are reviewed. Organic and inorganic heat storage materials classified as paraffins, fatty acids, inorganic salt hydrates and eutectic compounds are considered. The melting and freezing behavior of the various substances is investigated using the techniques of Thermal Analysis and Differential Scanning Calorimetry. The importance of thermal cycling tests for establishing the long-term stability of the storage materials is discussed. Finally, some data pertaining to the corrosion compatibility of heat-of-fusion substances with conventional materials of construction is presented.

1983-01-01

276

Application of pumped storage plants in the control of the Slovak power system and the possibility of pumped storage plant Ipel exploitation towards the year 2010  

International Nuclear Information System (INIS)

The paper deals with the exploitation of the pumped storage plants for the control of the Slovak power system. For that purpose current utilization of pumped storage plants currently in operation was analyzed from the point of view of their part in the operation control of the Slovak power system. The aim of this analysis was to exploit knowledge gained so far for the future outlook up to the year 2010, including the evaluation of the need to construct pumped storage plant Ipel with a weekly storage cycle. (author).

1997-05-13

277

Underground reservoirs for high-head pumped-storage stations  

Science.gov (United States)

The advantages of using heads of around 1000 m in conjunction with underground location of the lower reservoirs for pumped storage plants are described, and the possible layouts, equipment, and construction methods are discussed.

1973-03-01

278

Theoretical Basis of Protocols for Seed Storage  

UK PubMed Central (United Kingdom)

The protocols presently established for optimum seed storage do not account for the chemical composition of different seed species, the physiological status of the seed, and the physical status of water...Full Text Available

1990-11-01

279

Molten Boron Phase-Change Thermal Energy Storage ...  

Science.gov (United States)

... Advanced thermal storage systems based on very high temperature solid materials such as boron carbide or graphite have been investigated for ...

2011-06-01

280

Hydrogen energy storage: hydrogen and oxygen storage subsystems  

Energy Technology Data Exchange (ETDEWEB)

Hydrogen seems to possess all the characteristics to store the excess of electrical energy produced during off-peak periods. Hydrogen energy storage plants could be environmentally non-polluting, easy to place, not sensible to load variation, unbounded in size, efficient and safe. These last two features seem to contradict one another. An option that could give a reliable solution is the storage of hydrogen in metal hydride and the storage of oxygen as a liquid. Such a choice is probably the safest one to make and allows the achievement of efficiencies comparable to those obtainable with gaseous storage of both electrolytic products. The power consumption for H{sub 2} and O{sub 2} storage is only 3% of the total energy stored and the charging ratio approaches the values obtained with hydro-pumped storage plants. (Author)

1997-12-31

281

Firearm ownership and storage practices in Pennsylvania homes.  

UK PubMed Central (United Kingdom)

OBJECTIVE: To determine the household prevalence of firearms in Pennsylvania, and describe the storage practices for these weapons. DESIGN: A statewide telephone survey of 3,620 Pennsylvania adults...Full Text Available

1996-12-01

282

Effect of dry and wet storage at cool temperatures on the post-harvest performance of Ranunculus asiaticus L. flowers  

British Library Electronic Table of Contents (United Kingdom)

A study was undertaken to assess the effect of different storage temperatures on senescence and postharvest performance of isolated flowers of Ranunculus asiaticus L.. The main aim of the work was to develop a cost-effective storage protocol to reduce the postharvest losses and to bring out the transportation of cut flowers of R. Asiaticus. The flowers were subjected to two different storage treatments, dry storage and wet storage, and their postharvest performance was compared under laboratory conditions. For this purpose, the buds were harvested at 8:00 AM at loose bud stage (Stage II of flower development). The harvested buds were cut to a uniform size of 15 cm and processed for dry or wet storage. For dry storage, the buds were packed after wrapping them in moistened filter papers and ...

2011-01-01

283

Coastal Food Storage Locations- Kenai Fjords National Park  

Science.gov (United States)

This layer represents the different food storage facilities available at backcountry campsites along the coast of Kenai Fjords National Park. Site locations ... ...

284

Benefits and applications of modular hydroelectric pumped storage  

International Nuclear Information System (INIS)

This paper reports on hydroelectric pumped storage which is the only proven and most efficient technology available for energy storage. It is used by utilities to provide peak and intermediate power and to optimize overall system performance. Because of increased environmental and regulatory constraints, few acceptable sites, long schedules, and huge financial commitments, large conventional pumped storage plants, are now virtually impossible to build. As an alternative, small modular pumped storage, with project sizes ranging from 25 MW to 200 MW, was created to overcome the difficulties of conventional projects. The modular approach involves standardizing the elements of a pumped storage plant by utilizing specialized siting techniques and optimizing design, equipment, and construction. Compared with conventional pumped storage, the modular design can reduce ...

1991-07-24

285

Waste management plan for the APT  

Energy Technology Data Exchange (ETDEWEB)

This revision of the APT Waste Management Plan details the waste management requirements and issues specific to the APT plant for design considerations, construction, and operation. The APT Waste Management Plan is by its nature a living document and will be reviewed at least annually and revised as required.

1997-08-22

288

Nuclear waste management: a perspective  

Energy Technology Data Exchange (ETDEWEB)

The scope of our problems with nuclear waste management is outlined. Present and future inventories of nuclear wastes are assessed for risk. A discussion of what is presently being done to solve waste management problems and what might be done in the future are presented. (DC)

1980-01-01

291

E-waste hazard: The impending challenge  

UK PubMed Central (United Kingdom)

Electronic waste or e-waste is one of the rapidly growing problems of the world. E-waste comprises of a multitude of components, some containing toxic substances that can have an adverse impact on human...Full Text Available

2008-08-01

295

40 CFR 261.2 - Definition of solid waste.  

Science.gov (United States)

...2009-07-01 false Definition of solid waste. 261.2 Section 261.2 Protection...PROTECTION AGENCY (CONTINUED) SOLID WASTES (CONTINUED) IDENTIFICATION AND LISTING OF HAZARDOUS WASTE General § 261.2 Definition...

2009-07-01

296

Ecological utilization of wastes. A manual for optimum waste management concepts. 3. rev. ed. Oekologische Muellverwertung. Handbuch fuer optimale Abfall-Konzepte  

Energy Technology Data Exchange (ETDEWEB)

From out of the numerous technical alternatives the manual develops a waste management concept with emphasis on methods which can be coordinated for maximum ecological use and minimum economic costs. A clear-cut analysis of the present state of waste utilization and waste disposal in the Federal Republic of Germany (chapter 1) is followed by a detailed description of conventional and modern state-of-the-art waste utilization methods based on ecological evaluation criteria (chapter 3). An optimum waste utilization concept for defined quantities of wastes is derived from the ecological and economic comparison of waste utilization techniques given in chapter 3. Chapter 4 points out different variants of waste utilization and waste disposal methods and shows how to determine the optimum variant of the ...

1991-01-01

297

Thermal waste disposal and utilization; Waste management in accordance with the German Municipal Waste Disposal Regulations. Abfaelle thermisch entsorgen und verwerten; Die Verwaltungsvorschrift TA Siedlungsabfall praegt gesamte Abfallbehandlung  

Energy Technology Data Exchange (ETDEWEB)

Drastic changes in waste management procedures are expected from the German Municipal Waste Disposal Regulations which became effective on June 1, 1993. Waste disposal will be subject to certain restrictions which, e.g. demand that wastes must be pretreated and inerted before they are stored. These regulations favor thermal waste disposal methods such as the carbonization/combustion method which is planned for a commercial-scale plant in the city of Fuerth. (orig./BBR)

1993-09-01

298

Surface Crystallization and Composition of Spinel and Acmite in High-Level Waste Glass  

Science.gov (United States)

Surface crystallization and surface-to-bulk ratio in high-level waste glasses.

2000-07-10

299

Safe management of wastes from the mining and milling of Uranium and Thorium ores  

CERN Document Server

Safe management of wastes from the mining and milling of Uranium and Thorium ores

1987-01-01

300

Hazardous Waste Management on the Farm  

Science.gov (United States)

Sep 2, 2008 ... Abstract: This tutorial is intended to serve as a guide towards proper hazardous waste management. Knowing the regulations, different ...

301

Control of Effluent Gases from Solid Waste Processing Using Carbon Nanotubes  

Science.gov (United States)

One of the major problems associated with solid waste processing technologies is the release of

2005-01-01

303

Request for interim approval to operate Trench 94 of the 218-E-12B Burial Ground as a chemical waste landfill for disposal of polychlorinated biphenyl waste in submarine reactor compartments. Revision 2.  

Science.gov (United States)

This request is submitted to seek interim approval to operate a Toxic Substances Control Act (TSCA) of 1976 chemical waste landfill for the disposal of polychlorinated biphenyl (PCB) waste. Operation of a chemical waste landfill for disposal of PCB waste ...

1994-01-01

304

Radioactive and mixed waste management plan for the Lawrence Berkeley Laboratory Hazardous Waste Handling Facility  

Energy Technology Data Exchange (ETDEWEB)

This Radioactive and Mixed Waste Management Plan for the Hazardous Waste Handling Facility at Lawrence Berkeley Laboratory is written to meet the requirements for an annual report of radioactive and mixed waste management activities outlined in DOE Order 5820.2A. Radioactive and mixed waste management activities during FY 1994 listed here include principal regulatory and environmental issues and the degree to which planned activities were accomplished.

1995-01-01

305

Composting - environmentally compatible waste disposal - one of the incredients of waste management  

Energy Technology Data Exchange (ETDEWEB)

Considering the fact that more than 40% of all household wastes are organic wastes composting could be an excellent relief and complement to other waste disposal methods (e.g. combustion or direct landfills). Provided the right conditions household wastes could be composted together with sewage sludges and manures. The paper discusses the legal aspects, quantitative evaluations, conveying systems, as well as the compost utilization and marketing aspects valid for the Federal Republic of Germany.

1988-09-20

306

Charging generators for waste management costs  

Energy Technology Data Exchange (ETDEWEB)

Implementation of a plan to charge waste management costs to the facility that generates such waste requires a long-term commitment and consistent administration. The benefit is that generators are provided the incentive to optimize waste management practices if the charges are appropriately applied. This paper summarizes (1) a plan to charge waste generators, (2) the administrative structure of the plan, (3) a comparison between the rate structure and changes in waste disposal operations, and (4) issues that have surfaced as the plan is implemented. 2 refs., 1 fig., 1 tab.

1988-01-01

307

AVLIS production plant waste management plan  

Energy Technology Data Exchange (ETDEWEB)

Following the executive summary, this document contains the following: (1) waste management facilities design objectives; (2) AVLIS production plant wastes; (3) waste management design criteria; (4) waste management plan description; and (5) waste management plan implementation. 17 figures, 18 tables.

1984-11-15

308

The feasibility study of hot cell decontamination by the PFC spray method  

International Nuclear Information System (INIS)

The characteristics of per-fluorocarbon compounds (PFC) are colorless, non-toxic, easily vaporized and nonflammable. Also, some of them are liquids of a high density, low surface tension, low latent heat and low specific heat. These particular chemical and physical properties of fluoro-organic compounds permit their use in very different fields such as electronics, medicine, tribology, nuclear and material science. The Sonatol process was developed under a contract with the DOE. The Sonatol process uses an ultrasonic agitation in a PFC solution that contains a fluorinated surfactant to remove radioactive particles from surfaces. Filtering the suspended particles allows the solutions to be reused indefinitely. They applied the Sonatol process to the decontamination of a heterogeneous legacy Pu-238 waste that exhibited an excessive hydrogen gas generation, which prevents a transportation of such a waste to a Waste Isolation ...

2008-01-01

309

Hospital waste management in Lebanon  

International Nuclear Information System (INIS)

Hospital wastes comprises approximately 80% domestic waste components, also known as non-risk waste and 20% hazardous or risk waste. The 20% of the hospital waste stream or the risk waste (also known as infectious, medical, clinical wastes) comprises components which could be potentially contaminated with infections, chemical or radioactive agents. Therefore, it should be handled and disposed of in such a manner as to minimize potential human exposure and cross-contamination. Hospital risk waste and be subdivided into seven general categories as follows: infections, anatomical/pathological, chemical, pharmaceutical, radioactive waste, sharps and pressurised containers. These waste categories are generated by many types of health care establishments, including hospitals, clinics, ...

1999-06-02

310

Reducing Rice Seed Storage Protein Accumulation Leads to Changes in Nutrient Quality and Storage Organelle Formation1[W][OA]  

UK PubMed Central (United Kingdom)

Rice (Oryza sativa) seed storage proteins (SSPs) are synthesized and deposited in storage organelles in the endosperm during seed maturation as a nitrogen source for germinating seedlings....Full Text Available

2010-12-01

316

First-generation fuel cell demonstration and commercialization activities  

International Nuclear Information System (INIS)

... electric utilities electrochemistry energy storage fuel cells organizational models

318

Energy storage systems program report for FY1996  

Energy Technology Data Exchange (ETDEWEB)

Sandia National Laboratories, New Mexico, conducts the Energy Storage Systems Program, which is sponsored by the US Department of Energy`s Office of Utility Technologies. The goal of this program is to assist industry in developing cost-effective energy storage systems as a resource option by 2000. Sandia is responsible for the engineering analyses, contracted development, and testing of energy storage systems for stationary applications. This report details the technical achievements realized during fiscal year 1996.

1997-05-01

319

Efficiency of preliminary transmutation of actinides before ultimate storage  

International Nuclear Information System (INIS)

The concept of preliminary transmutation of minor actinides before placement to the long-term storage is considered. The purpose of such preliminary transmutation before ultimate storage is to incinerate a part of actinides and to transform another part into new actinides providing low level of radiotoxicity accumulated in the storage. Modes of transmutation in reactors of PWR, PHWR (CANDU), and Superfenix types are compared. Among power reactors, heavy-water PHWR type reactor is most acceptable for preliminary transmutation. (author)

2003-04-20

321

Effect of a pumped storage plant on the generation reliability of the Taiwan power system  

Energy Technology Data Exchange (ETDEWEB)

A novel approach to the reliability analysis of a power system with both hydro and pumped storage plants is presented in this paper. The proposed method is based on the concept of peak shaving for the hydro and pumped storage units. Different values of the stored energy of the pumped storage units are employed to demonstrate their effect on the generation reliability of a power system. The proposed scheme has been applied successfully to the reliability analysis of Taiwan power system.

1986-05-01

328

Waste recycling as evaluated from the viewpoint of energy environment, mainly about plastics; Haikibutsu recycle no energy kankyomen kara no hyoka. Plastic wo chushin to shite  

Energy Technology Data Exchange (ETDEWEB)

Some comments are given on the recycling of waste, mainly plastics, as evaluated from the viewpoint of energy environment. Discussed about the waste in general are the definition and classification, generation and resource recovery rates, current state of recycling, problems about recycling, related legislation, and current conditions overseas. Discussed about the treatment and recycling of plastics waste are the characters and use of plastic product, current state of waste plastics treatment, current state of waste plastics recycling (material recycling, thermal recycling), energy recovery by thermal recycling, quantity recyclable from waste plastics, energy consumption and cost for waste plastics recycling, effect and impact of increase in waste plastics in case material recycling is forwarded, and prospect of ...

1996-05-01

329

Hanford Waste Vitrification Plant Quality Assurance Program description for high-level waste form development and qualification  

International Nuclear Information System (INIS)

The Hanford Waste Vitrification Plant Project has been established to convert the high-level radioactive waste associated with nuclear defense production at the Hanford Site into a waste form suitable for disposal in a deep geologic repository. The Hanford Waste Vitrification Plant will mix processed radioactive waste with borosilicate material, then heat the mixture to its melting point (vitrification) to forin a glass-like substance that traps the radionuclides in the glass matrix upon cooling. The Hanford Waste Vitrification Plant Quality Assurance Program has been established to support the mission of the Hanford Waste Vitrification Plant. This Quality Assurance Program Description has been written to document the Hanford Waste Vitrification Plant Quality Assurance Program.

1993-05-06

330

Storage of electric energy gained from renewable sources  

Energy Technology Data Exchange (ETDEWEB)

This paper discussed issues related to the storage of electricity produced from renewable energy sources. Storage systems currently used by distribution systems were reviewed. The study showed that successful storage systems ensure high charging and discharging rates for shorter periods of time. Systems with high storage capacities must also be able to store energy for longer periods of time than traditional energy storage systems. Systems include pumped storage plants; electro-chemical accumulators; compressed air accumulators; and redox flow batteries. Hydrogen technologies for the storage of electric energy from renewable sources were reviewed. The paper also outlined energy storage and fuel cell research currently being conducted by researchers in the Czech Republic. The study concluded by stating that new energy ...

2009-03-11

331

Waste laws. Waste Classification Ordinance. Residual Material Classification Ordinance. The Waste Technical Code. Ordinance on the Monitoring of Wastes and Residual Material. Ordinance on the Ban on CFCs and Halogenated Hydrocarbons. Packaging Ordinance. Sewage Ordinance. Text edition with index and an introduction by Dr. Clemens Weidemann. As of May 15, 1992. Abfallgesetz. AbfallbestimmungsV. ReststoffbestimmungsV. TA Abfall. Abfall- und ReststoffueberwachungsV. FCKW-Halon-VerbotsV. VerpackungsV. KlaerschlammV. Textausgabe mit Sachverzeichnis und einer Einfuehrung von Rechtsanwalt Dr. Clemens Weidemann. Stand: 15. Mai 1992  

Energy Technology Data Exchange (ETDEWEB)

The turbulent history of legislature concerned with the waste-management industry and the amount of material on this subject as well as the significance of the material in its own right led to the decision to publish all legal regulations on waste in one volume. It includes above all the Waste Law, Regulations on Determination of Waste, Regulations on Determination of Residual Products, Technical Instructions for Waste, Regulations for Monitoring Waste and Residual Products, Regulations on Probition from the Use of Chlorofluorohydrocarbons and Halon, Regulations on Packaging and Regulations on Sewage Sludge. The introduction explains the development and the role of the Waste Law and its applicability, goals and principles: The concept of waste, avoidance of waste, avoidance of ...

1992-01-01

332

Framework for managing wastes from oil and gas exploration and production (E&P) sites.  

Energy Technology Data Exchange (ETDEWEB)

Oil and gas companies operate in many countries around the world. Their exploration and production (E&P) operations generate many kinds of waste that must be carefully and appropriately managed. Some of these wastes are inherently part of the E&P process; examples are drilling wastes and produced water. Other wastes are generic industrial wastes that are not unique to E&P activities, such as painting wastes and scrap metal. Still other wastes are associated with the presence of workers at the site; these include trash, food waste, and laundry wash water. In some host countries, mature environmental regulatory programs are in place that provide for various waste management options on the basis of the characteristics of the wastes and the environmental ...

2007-09-15

333

Development and pilot demonstration program of a waste minimization plan at Argonne National Laboratory  

Energy Technology Data Exchange (ETDEWEB)

In response to US Department of Energy directives, Argonne National Laboratory (ANL) has developed a waste minimization plan aimed at reducing the amount of wastes at this national research and development laboratory. Activities at ANL are primarily research- oriented and as such affect the amount and type of source reduction that can be achieved at this facility. The objective of ANL's waste minimization program is to cost-effectively reduce all types of wastes, including hazardous, mixed, radioactive, and nonhazardous wastes. The ANL Waste Minimization Plan uses a waste minimization audit as a systematic procedure to determine opportunities to reduce or eliminate waste. To facilitate these audits, a computerized bar-coding procedure is being implemented at ANL to track hazardous wastes ...

1991-01-01

334

Attenuation of heavy metal leaching from hazardous wastes by co-disposal of wastes  

Energy Technology Data Exchange (ETDEWEB)

The potential hazard of landfill wastes was previously evaluated by examining the extraction procedures for individual waste, although various wastes were co-disposed of in actual landfills. This paper investigates the reduction of extraction-procedure toxicity by co-disposing various combinations of two wastes. When two wastes are mixed homogeneously, the extraction of heavy metals from the waste mixture is critically affected by the extract pH. Thus, co-disposal wastes will have a resultant pH between the pH values of its constituent. The lower the resultant pH, the lower the concentrations of heavy metals in the extract. When these wastes are extracted sequentially, the latter extracted waste has a stronger influence on the final concentration of heavy metals in the extract. Small-scale lysimeter ...

1996-12-31

335

Pumped-storage hydropower schemes  

Energy Technology Data Exchange (ETDEWEB)

The general types of pumped-storage plants and considerations for determining their need, use, and selection are presented. A brief discussion of TVA's experience on two pumped-storage schemes is included. Pumped-storage plants have become an integral part of many hydropower systems. Most of these systems use pumped-storage plants to meet power requirements during the peak load demands. In any application, large or small, the expected load demand and supply source must be identified to select the best scheme required for the particular system.

1984-01-01

336

Pumped storage plants. Status and perspectives  

Energy Technology Data Exchange (ETDEWEB)

Pumped storage plants (PSP) enable the storage of energy with rated capacities of order of GW at a single site. Reservoirs allow charging and discharging times of at least hours, sometimes days or even up to several weeks. Short ramp-up times permit the participation in the secondary reserve market as a standing reserve. For bulk energy storage, PSP reach the lowest, specific costs. In the EU27 countries, Norway and Switzerland, a total of 44 GW of pumped storage capacity is installed. The utilisation of PSP strongly correlates with the amount of conventional generation capacity, rather than with topographical options. (orig.)

2011-07-01

337

Optimal generation planning for a thermal system with pumped-storage based on analytical production costing model  

Energy Technology Data Exchange (ETDEWEB)

This paper presents a new algorithm for the optimal long-range generation planning for a thermal system with pumped-storage plants. The algorithm is based upon the analytical production costing model developed under the assumption of Gaussian probabilistic distribution of random load fluctuations and plant outages. The optimization problem consists of the master problem to determine the annual investment, and the pumped-storage subproblem to determine the optimal pumped-storage operation. The master problem is formulated as a Hamiltonian minimization problem, and the pumped-storage subproblem is solved using the concept of peak-shaving operation on the original load curve.

1986-01-01

338

Optimal generation planning for a thermal system with pumped-storage based on analytical production costing model  

Energy Technology Data Exchange (ETDEWEB)

This paper presents a new algorithm for the optimal long-range generation planning for a thermal system with pumped-storage plants. The algorithm is based upon the analytical production costing model developed under the assumption of Gaussian probabilistic distribution of random load fluctuations and plant outages. The optimization problem consists of the master problem to determine the annual investment, and the pumped-storage subproblem to determine the optimal pumped-storage operation. The master problem is formulated as a Hamiltonian minimization problem, and the pumped-storage subproblem is solved using the concept of peak-shaving operation on the original load curve.

1987-05-01

339

Modeling of battery energy storage in the National Energy Modeling System  

Energy Technology Data Exchange (ETDEWEB)

The National Energy Modeling System (NEMS) developed by the U.S. Department of Energy`s Energy Information Administration is a well-recognized model that is used to project the potential impact of new electric generation technologies. The NEMS model does not presently have the capability to model energy storage on the national grid. The scope of this study was to assess the feasibility of, and make recommendations for, the modeling of battery energy storage systems in the Electricity Market of the NEMS. Incorporating storage within the NEMS will allow the national benefits of storage technologies to be evaluated.

1997-12-01

340

Survey reveals Europe's refinery-waste disposal methods, amounts, and costs  

Energy Technology Data Exchange (ETDEWEB)

Results of a survey conducted by Concawe on 75 oil refineries in Europe show that the total quantity of waste requiring disposal in 1986 was 0.5 million metric tons. This quantity of waste is but 0.13% of the total refinery throughput of 387 million metric tons during 1986. The survey revealed a wide range of disposal costs, depending on the particular properties of the waste and local conditions. A summary of total waste generation and how the waste is disposed of is shown. Details on the types of waste disposed, the disposal methods used, and the costs of disposal are detailed in this excerpt from the Concawe survey.

1989-08-28

341

ICDF Complex Operations Waste Management Plan  

Science.gov (United States)

This Waste Management Plan functions as a management and planning tool for managing waste streams generated as a result of operations at the Idaho CERCLA Disposal Facility (ICDF) Complex. The waste management activities described in this plan support the selected remedy presented in the Waste Area Group 3, Operable Unit 3-13 Final Record of Decision for the operation of the Idaho CERCLA Disposal Facility Complex. This plan identifies the types of waste that are anticipated during operations at the Idaho CERCLA Disposal Facility Complex. In addition, this plan presents management strategies and disposition for these anticipated waste streams.

2006-12-01

342

Defense remote-handled transuranic waste implementation plan: Transuranic Waste Program System Integration Office  

Energy Technology Data Exchange (ETDEWEB)

This document presents a detailed schedule for the implementation of the strategy for managing defense remote-handled (RH) transuranic (TRU) waste. The baseline management strategy was defined in the Defense Remote-Handled Transuranic Waste Cost/Schedule Optimization Study and is summarized in this document. Also included are revised RH TRU waste inventory projections, current site management plans, a list of key decision points and milestones, and a discussion of uncertainties associated with management of RH TRU waste. The plans are summarized in a detailed schedule diagram and in an RH TRU waste work off diagram. 9 refs., 5 figs., 4 tabs.

1988-01-01

343

The radioecological risk of decommissioning of nuclear submarines. Possible accidents and normal conditions  

International Nuclear Information System (INIS)

In the report the results of the estimations of radiological risk of various stages of decommissioning of nuclear submarines are presented. At occurrence on nuclear submarine the heavy failure, relating to the class hypotetical volume of acting of radionuclides in atmosphere can reach 1.6E(15) Bq. Results of estimations probable doses on an axis of a trace of a radioactive loop show, that at distribution of radionuclides during atmospheric carry to 'agreed' settlement (500-1000 m) the maximum doses on its territory can make: about 6.0E(-3) Sv (for the whole body); 3.0E(-3) Gy for the leather (basal layer); 6.3E(-2) Gy for the lungs (acute exposure) and up to 1.8 Gy for the thyroid gland. Hypotetical failure for the estimation of the greatest possible radioecological consequences for hydrobiocenosis is considering, connected with single discharge of liquid radioactive waste (LRW) in water area. At navigating failure of the tanker with LRW in water area can arrive ...

2000-05-01

344

Streams of solid municipal wastes. Evaluation of data on the basis of waste follow-up system; Kiinteaen yhdyskuntajaetteen virrat: aineistotarkastelua jaetealan seurantajaerjestelmaen avulla  

Energy Technology Data Exchange (ETDEWEB)

The follow-up system for wastes (JAeSTI), developed at the end of the 1990s, forms a basis for today's followup activities in Finland. JAeSTI relies on an environmental protection database, the compliance monitoring system VAHTI operated by the environmental authorities. Waste followup and waste statistics depend very much on the annual waste quantities recorded in the VAHTI system. In the KYJ-project the coverage and reliability of the data in the VAHTI system was evaluated as for the streams of solid municipal waste. The project also included the compiling of national statistics on municipal waste for the year 2000. The project used other information sources, too, such as statistics compiled when the National Waste Plan and regional waste plans were revised in 2002. In addition, the extent and quantity of ...

2004-07-01

345

Vulnerability of soil resources to heavy metals contamination in Central Bekaa-Lebanon  

International Nuclear Information System (INIS)

Full text.Changes in land use and urbanization yield more pressure put on limited soil and water resources, including the risk of pollution with toxic heavy metals. The study area lies in the Bekaa valley totaling about 12753 ha. The valley receives from the west torrential fan deposits and a mixture of colluvial and alluvial material. The principal soil classes are Fluvisols, Cambisols, Regosols, Vertisols and Luvisols. The area is populated and also the most important agricultural part of the plain. Agriculture in the plain is being practiced mainly with cash, field crops and vegetables. The western surrounding area is being used mainly for terraced fruit trees. This Arab-German Technical Cooperation Project (ACSAD-BGR) aimed, following the ISO standards and Eikman-Klocke recommendations, at investigating the nature of the extends of soil pollution by heavy metals in two pilot areas: The central Bekaa-Lebanon and Ghouta-Damascus. Different institutions cooperate in the implementation ...

2000-11-23

346

Towards a higher energy efficiency and lower carbon society the European approach and experience  

International Nuclear Information System (INIS)

The use of natural energy sources and their conversion to secondary forms of energy are a crucial base for the development of our society with its continuous change of requirements due to an increase in population and the broadening of the needs in our modern life. As a consequence the consumption of primary energy resources rose drastically worldwide during the last 5 decades in particular in the industrialized regions such as Europe. Parallel in time the increasing awareness of negative effects of fuel dependent pollution on the environment and the introduction of stringent emission control regulations about 3 decades ago initiated extensive development and retrofit activities resulting in the today applied high level state of the art. As an additional challenge the worldwide debate about the potential effects of the emission of the s.c green house gases on the global climate in particular carbon dioxide from the use of predominantly fossil fuels have initiated in the European Union ...

2010-07-26

347

The Waste of the World  

Environmental Research Database

ObjectivesThis programme aims; To rethink how waste is thought about in social science; To provide a global analysis of waste; To examine how rethinking waste impinges on core social science concerns, notably: economies, researching globalisation, hazards and risk, and materiality. Social science understandings of waste position waste as the end-point of production and consumption, and see waste as a question of disposal.DescriptionThe Waste of the World is a five year research programme funded under ESRC's Large Grant Scheme. It brings together researchers in geography, anthropology and materials science from the University of Sheffield, Durham University, University College London and Goldsmiths College London, and connects the UK with South Asia (particularly India and Bangladesh), as well as the US, Europe and Kazakhstan. The ...

2011-01-30

348

Operable Unit 3-13, Group 3, Other Surface Soils Remediation Sets 4-6 (Phase II) Waste Management Plan  

Energy Technology Data Exchange (ETDEWEB)

This Waste Management Plan describes waste management and waste minimization activities for Group 3, Other Surface Soils Remediation Sets 4-6 (Phase II) at the Idaho Nuclear Technology and Engineering Center located within the Idaho National Laboratory. The waste management activities described in this plan support the selected response action presented in the Final Record of Decision for Idaho Nuclear Technology and Engineering Center, Operable Unit 3-13. This plan identifies the waste streams that will be generated during implementation of the remedial action and presents plans for waste minimization, waste management strategies, and waste disposition.

2006-07-01

349

Treatment of radioactive metallic waste by the electro-slag melting method  

Energy Technology Data Exchange (ETDEWEB)

The applicability of the electro-slag melting method for treating plutonium contaminated metallic waste was studied. A 100kg test furnace was built and simulated metallic waste was melted and solidified in this furnace. Waste volume was reduced to 1/25 with a decontamination factor of 25 and the slag and the copper mold are repeatedly usable. The process is expected to be employed in the project of PWTF (Plutonium contaminated Waste Treatment Facilities).

1983-01-01

350

Request for interim approval to operate 218-E-12B Trench 94 as a chemical waste landfill for disposal of polychlorinated biphenyl wastes in submarine reactor compartments.  

Science.gov (United States)

This request is submitted to seek interim approval to operate a chemical waste landfill for the disposal of polychlorinated biphenyl (PCB) wastes. This request covers only the disposal of small quantities of solid PCB wastes contained in decommissioned su...

1990-01-01

351

Projected radionuclide inventories of DWPF glass from current waste at time of production  

Energy Technology Data Exchange (ETDEWEB)

The Waste Acceptance Preliminary Specifications (WAPS) require that the DWPF estimate the inventory of long-lived radionuclides present in the waste glass, and report the values in the Waste Form Qualification Report. In this report, conservative (biased high) estimates of the radionuclide inventory of glass produced from waste currently in the Tank Farm are provided. In most cases, these calculated values compare favorably with actual data. In those cases where the agreement is not good, the values reported here are conservative.

1993-02-04

352

Industrial waste and pollution in Mongolia  

Energy Technology Data Exchange (ETDEWEB)

This paper very briefly outlines hazardous waste management issues, including regulations, in Mongolia. Air, water, and soil pollutants are identified and placed in context with climatic, social, and economic circumstances. The primary need identified is technology for the collection and disposal of solid wastes. Municipal waste problems include rapid urbanization and lack of sanitary landfills. Industrial wastes of concern are identified from the mining and leather industries. 4 refs., 2 tabs.

1996-12-31

353

Finally authorized supplementary report to the review on waste disposal in the Copenhagen area 1988. [Denmark]. Endelig godkendt bilagsrapport til affaldsredegoerelse for hovedstadsregionen 1988; Bilagsrapport nr. 1  

Energy Technology Data Exchange (ETDEWEB)

A supplementary report to the plan for waste disposal in the Copenhagen area, Denmark. It presents a mapping of wastes and waste flow in invidual areas, a description of recycling methods and waste collection systems. In addition legislative demands and potentials are dealth with. (CLS).

1988-07-01

354

Advanced Underground Gas Storage Concepts: Refrigerated-Mined Cavern Storage, Final Report  

Energy Technology Data Exchange (ETDEWEB)

Over the past 40 years, cavern storage of LPG's, petrochemicals, such as ethylene and propylene, and other petroleum products has increased dramatically. In 1991, the Gas Processors Association (GPA) lists the total U.S. underground storage capacity for LPG's and related products of approximately 519 million barrels (82.5 million cubic meters) in 1,122 separate caverns. Of this total, 70 are hard rock caverns and the remaining 1,052 are caverns in salt deposits. However, along the eastern seaboard of the U.S. and the Pacific northwest, salt deposits are not available and therefore, storage in hard rocks is required. Limited demand and high cost has prevented the construction of hard rock caverns in this country for a number of years. The storage of natural gas in mined caverns may prove technically feasible if the geology of the targeted market area is suitable; and economically ...

1998-09-30

355

Transport of symmetric mass region fission products at the Oklo natural reactors  

International Nuclear Information System (INIS)

The isotopic composition of Pd, Ag, Cd and Te has been measured by solid source mass spectrometry for four samples from reactor zones 2, 3-4, 5-6 and 7, and from four host rock samples external to the reactor zones from the Oklo mine site. The concentrations of these elements have also been determined in the eight samples using the stable isotope dilution technique. Cumulative fission yields have been derived from the reactor zone samples after correcting where necessary for the terrestrial component of the element concerned. It has been shown that fission-produced Pd and Te are retained almost in their entirety in the uraninite reactor zone samples, whereas a significant fraction of fission-produced Ag and Cd have migrated from the reactor zones. Fission product Cd is observed in the host rock samples, whereas no strong evidence of fission-produced Ag could be found. This the fission-produced Ag which has migrated from the reactor zones has not been retained in the four host rock ...

1984-01-01

356

Preliminary studies of tunnel interface response modeling using test data from underground storage facilities.  

Energy Technology Data Exchange (ETDEWEB)

In attempting to detect and map out underground facilities, whether they be large-scale hardened deeply-buried targets (HDBT's) or small-scale tunnels for clandestine border or perimeter crossing, seismic imaging using reflections from the tunnel interface has been seen as one of the better ways to both detect and delineate tunnels from the surface. The large seismic impedance contrast at the tunnel/rock boundary should provide a strong, distinguishable seismic response, but in practice, such strong indicators are often lacking. One explanation for the lack of a good seismic reflection at such a strong contrast boundary is that the damage caused by the tunneling itself creates a zone of altered seismic properties that significantly changes the nature of this boundary. This report examines existing geomechanical data that define the extent of an excavation damage zone around underground tunnels, and the potential impact on rock properties such as P-wave and S-wave velocities. ...

2010-11-01

357

Port Pirie rare earths plant stage 3  

International Nuclear Information System (INIS)

SX Holdings Limited intends to establish a rare earths plant at Port Pirie, South Australia. The proposal involves three stages of development, Stage 3 being to develop a monazite cracking plant and associated rare earths separation facility with the capacity to process up to 8,000 t/a of monazite-type ores. The proposed initial capacity is 4,000 t/a. This Draft Environmental Impact Statement relates to Stage 3 and is based on a monazite processing capacity of 8,000 t/a. The justification of the project is given in terms of use and the market for rare earths, the economic and environmental benefits of the proposal, the site selection process, site rehabilitation, and the consequences of not proceeding. A detailed description of the project is given, including the treatment process, site development and facilities, the supply of raw materials, product and waste handling, transport and storage, plant commissioning, operation and decommissioning, ...

358

Occupational dose reduction at Department of Energy contractor facilities: Bibliography of selected readings in radiation protection and ALARA; Volume 5  

Energy Technology Data Exchange (ETDEWEB)

Promoting the exchange of information related to implementation of the As Low as Reasonably Achievable (ALARA) philosophy is a continuing objective for the Department of Energy (DOE). This report was prepared by the Brookhaven National Laboratory (BNL) ALARA Center for the DOE Office of Health. It contains the fifth in a series of bibliographies on dose reduction at DOE facilities. The BNL ALARA Center was originally established in 1983 under the sponsorship of the Nuclear Regulatory Commission to monitor dose-reduction research and ALARA activities at nuclear power plants. This effort was expanded in 1988 by the DOE`s Office of Environment, Safety and Health, to include DOE nuclear facilities. This bibliography contains abstracts relating to various aspects of ALARA program implementation and dose-reduction activities, with a specific focus on DOE facilities. Abstracts included in this bibliography were selected from proceedings of technical meetings, journals, research reports, ...

1994-01-01

359

Occupational dose reduction at Department of Energy contractor facilities: Bibliography of selected readings in radiation protection and ALARA  

Energy Technology Data Exchange (ETDEWEB)

This bibliography contains abstracts relating to various aspects of ALARA program implementation and dose reduction activities, with a focus on DOE facilities. Abstracts included in this bibliography were selected from proceedings of technical meetings, journals, research reports, searches of the DOE Energy, Science and Technology Database (in general, the citation and abstract information is presented as obtained from this database), and reprints of published articles provided by the authors. Facility types and activities covered in the scope of this report include: radioactive waste, uranium enrichment, fuel fabrication, spent fuel storage and reprocessing, facility decommissioning, hot laboratories, tritium production, research, test and production reactors, weapons fabrication and testing, fusion, uranium and plutonium processing, radiography, and aocelerators. Information on improved shielding design, decontamination, containments, ...

1993-12-01

360

Isolated PWM DC-AC SICAM with an active capacitive voltage clamp[Pulse Density Modulated; Pulse Width Modulation  

Energy Technology Data Exchange (ETDEWEB)

In this report an isolated PWM DC-AC SICAM with an active capacitive voltage clamp is presented. AC-DC power supply is implemented in its simplest form: diode rectifier followed by a medium-size charge-storage capacitors and possibly with an EMC filter on the mains entrance. Isolation from the AC mains is achieved using a high frequency (HF) transformer, whose voltages are not audio-modulated. The latter simplifies the design and is expected to have many advantages over the approach where the transformer voltages are modulated in regards to the audio signal reference. Input stage is built as a DC-AC inverter (push-pull, half-bridge or a full-bridge) and operated with 50% duty cycle, with all the challenges to avoid transformer saturation and obtain symmetrical operation. On the secondary side the output section is implemented as rectifier+inverter AC-AC stage, i.e. a true bidirectional bridge, which operation is aimed towards amplification of the audio signal. In ...

2004-03-15

361

ICPES analyses using full image spectra and astronomical data fitting algorithms to provide diagnostic and result information  

Energy Technology Data Exchange (ETDEWEB)

ICP emission analyses are prone to errors due to changes in power level, nebulization rate, plasma temperature, and sample matrix. As a result, accurate analyses of complex samples often require frequent bracketing with matrix matched standards. Information needed to track and correct the matrix errors is contained in the emission spectrum. But most commercial software packages use only the analyte line emission to determine concentrations. Changes in plasma temperature and the nebulization rate are reflected by changes in the hydrogen line widths, the oxygen emission, and neutral ion line ratios. Argon and off-line emissions provide a measure to correct the power level and the background scattering occurring in the polychromator. The authors` studies indicated that changes in the intensity of the Ar 404.4 nm line readily flag most matrix and plasma condition modifications. Carbon lines can be used to monitor the impact of organics on the analyses and calcium and argon lines can be ...

1997-10-01

362

Fundamental Elements of Geologic C02 Sequestration in Saline Aquifers  

Energy Technology Data Exchange (ETDEWEB)

Geologic sequestration represents a promising strategy for isolating CO{sub 2} waste streams from the atmosphere. Successful implementation of this approach hinges on our ability to predict the relative effectiveness of subsurface CO{sub 2} migration and sequestration as a function of key target-formation and cap-rock properties, which will enable us to identify optimal sites and evaluate their long-term isolation performance. Quantifying this functional relationship requires a modeling capability that explicitly couples multiphase flow and kinetically controlled geochemical processes. We have developed a unique computational package that meets these criteria, and used it to model CO{sub 2} injection at Statoil's North-Sea Sleipner facility, the world's first saline-aquifer storage site. The package integrates a state-of-the-art reactive transport simulator (NUFT) with supporting geochemical software and databases (SUPCRT92). ...

2001-11-19

363

Fabrication of zircon for disposition of weapons plutonium  

International Nuclear Information System (INIS)

This is the final report of a one-year, Laboratory-Directed Research and Development (LDRD) project at the Los Alamos National Laboratory (LANL). In an effort to address the problems of long term storage and nuclear waste minimization, zircon has been proposed as a host medium for plutonium and other actinides recovered from dismantled nuclear weapons. The objective of this work is to investigate the feasibility of large scale fabrication of Pu-bearing zircon. Since PuO_2 is thermodynamically less stable than ZrO_2, it is expected that the process parameters determined for synthesizing ZrSiO_4 (zircon) would be applicable to those for PuSiO_4 (Pu-zircon). Furthermore, since the foremost concern in plutonium processing is the potential for contamination release, this work emphasizes the development of process parameters, using zircon first, to anticipate potential material problems in the containment system for reaction mixtures during ...

364

Environmental assessment for the recycling of slightly activated copper coil windings from the 184-Inch Cyclotron at Lawrence Berkeley Laboratory, Berkeley, California  

Energy Technology Data Exchange (ETDEWEB)

The proposed action is to recycle slightly activated copper that is currently stored in a warehouse leased by Lawrence Berkeley Laboratory (LBL) to a scrap metal dealer. Subsequent reutilization of the copper would be unrestricted. This document addresses the potential environmental effects of recycling and reutilizing the activated copper. In addition, the potential environmental effects of possible future uses by the dealer are addressed. Direct environmental effects from the proposed action are assessed, such as air emissions from reprocessing the activated copper, as well as indirect beneficial effects, such as averting air emissions that would result from mining and smelting an equivalent quantity of copper ore. Evaluation of the human health impacts of the proposed action focuses on the pertinent issues of radiological doses and protection of workers and the public. Five alternatives to the proposed action are considered, and their associated potential impacts are addressed. The ...

1993-08-02

365

Energy use in swine unit in the finishing system with waste treatment; Uso de energia em unidade suinicola em sistema de terminacao com tratamento de residuos  

Energy Technology Data Exchange (ETDEWEB)

The purpose of this study was to assess the energy flux and energetic balance related to the swine production and the recycling of residues generated by the system for utilization as organic fertilizers. The experiment was carried out at Vale dos Ipes Farm, located in the city of Ouro Verde do Oeste, in the Western of Parana State. One finishing phase swine unity containing 600 animals was monitored from January to June 2005. The treatment system is composed by one steel digester with capacity for 50 m{sup 3}, one sedimentation tank, one algae tank and one bio fertilizer storage tank. The swine barn cleaning is performed by dry scratching on a daily basis. The generated residues flow by gravitation through ducts towards the digester. The duration of the hydraulic retention period was 12 days. In the calculation of energetic efficiency, the energetic component ration is the greatest energetic cost in production system of finishing phase swine, corresponding to 95% ...

2006-07-01

366

Ecological risk assessments for protected migratory birds and marine species at Midway Atoll  

Energy Technology Data Exchange (ETDEWEB)

In June 1997, the US Navy plans to close its Naval Air Facility on Sand Island and transfer the atoll to the US Fish and Wildlife Service for use as a National Wildlife Refuge. Midway provides breeding and feeding habitat for migratory seabirds, terrestrial and marine mammals, sea turtles and other reptiles, and a variety of reef fishes and invertebrates. As part of the base closure and transfer process, 36 sites of potential environmental concern were identified on Sand and Eastern islands. These sites include landfills and uncontrolled disposal areas, hazardous materials storage areas, abandoned transformers, sewer outfalls, and other potential hazardous waste sites. Potential contaminants include pesticides, PAHs, PCBs, and heavy metals. A screening ecological risk assessment was performed at each site with a goal of determining whether contaminants could pose any current or future risks to protected migratory bird or marine mammal wildlife ...

1995-12-31

367

Dispersion of Metals from Abandoned Mines and their Effect on Biota in the Methow River, Okanogan County, Washington: Final Report 2002-2003.  

Energy Technology Data Exchange (ETDEWEB)

A study of mine-waste contamination effects on Methow River habitat on the eastern slopes of the north Cascade Mountains in Washington state, U.S.A., revealed impacts at ecosystem, community, population, individual, tissue, and cellular levels. Ore deposits in the area were mined for gold, silver, copper and zinc until the early 1950's, but the mines are now inactive. An above-and-below-mine approach was used to compare potentially impacted to control sites. The concentrations of eleven trace elements (i.e., Al, As, B, Ba, Cd, Cr, Cu, Mn, Pb, Se, and Zn) in Methow River sediments downstream from the abandoned mine sites were higher than background levels. Exposed trout and caddisfly larvae in the Methow River showed reduced growth compared to controls. Samples of liver from juvenile trout and small intestine from exposed caddisfly larvae were examined for evidence of metal accumulation, cytopathological change, and chemical toxicity. Morphological changes ...

2003-05-15

368

Closure Report for Corrective Action Unit 543: Liquid Disposal Units, Nevada Test Site, Nevada  

Energy Technology Data Exchange (ETDEWEB)

This Closure Report (CR) documents closure activities for Corrective Action Unit (CAU) 543, Liquid Disposal Units, according to the Federal Facility Agreement and Consent Order (FFACO, 1996) and the Corrective Action Plan (CAP) for CAU 543 (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office [NNSA/NSO], 2007). CAU 543 is located at the Nevada Test Site (NTS), Nevada (Figure 1), and consists of the following seven Corrective Action Sites (CASs): CAS 06-07-01, Decon Pad; CAS 15-01-03, Aboveground Storage Tank; CAS 15-04-01, Septic Tank; CAS 15-05-01, Leachfield; CAS 15-08-01, Liquid Manure Tank; CAS 15-23-01, Underground Radioactive Material Area; CAS 15-23-03, Contaminated Sump, Piping; and CAS 06-07-01 is located at the Decontamination Facility in Area 6, adjacent to Yucca Lake. The remaining CASs are located at the former U.S. Environmental Protection Agency (EPA) Farm in Area 15. The purpose of this CR is to provide a summary of ...

2008-01-01

369

Analysis and decision document in support of acquisition of steam supply for the Hanford 200 Area  

Energy Technology Data Exchange (ETDEWEB)

The US Department of Energy (DOE) is now evaluating its facility requirements in support of its cleanup mission at Hanford. One of the early findings is that the 200-Area steam plants, constructed in 1943, will not meet future space heating and process needs. Because the 200 Area will serve as the primary area for waste treatment and long-term storage, a reliable steam supply is a critical element of Hanford operations. This Analysis and Decision Document (ADD) is a preliminary review of the steam supply options available to the DOE. The ADD contains a comprehensive evaluation of the two major acquisition options: line-term versus privatization. It addresses the life-cycle costs associated with each alternative, as well as factors such as contracting requirements and the impact of market, safety, security, and regulatory issues. Specifically, this ADD documents current and future steam requirements for the 200 Area, describes alternatives ...

1992-02-01

370

Spent fuel consolidation in the 105KW Building fuel storage basin  

Energy Technology Data Exchange (ETDEWEB)

This study is one element of a larger engineering study effort by WHC to examine the feasibility of irradiated fuel and sludge consolidation in the KW Basin in response to TPA Milestone (target date) M-34-00-T03. The study concludes that up to 11,500 fuel storage canisters could be accommodated in the KW Basin with modifications. These modifications would include provisions for multi-tiered canister storage involving the fabrication and installation of new storage racks and installation of additional decay heat removal systems for control of basin water temperature. The ability of existing systems to control radionuclide concentrations in the basin water is examined. The study discusses requirements for spent nuclear fuel inventory given the proposed multi-tiered storage arrangement, the impact of the consolidated mass on the KW Basin structure, and criticality issues associated with multi-tiered ...

1994-09-23

371

Seismic stability analysis of the spent fuel storage structures for increase of storage capacity at Wolsung NPP  

Energy Technology Data Exchange (ETDEWEB)

This paper introduces the method of seismic stability analysis for the increase of fuel storage capacity of wet storage stacks by one or two more stack floor at Wolsung Nuclear Unit 2,3,4, which had been originally licensed assuming 16 tray stack-o-storage. As a basic procedure, tipping and sliding stability of the structure is checked at first thru seismic analysis and the resultant load from dynamic analysis is applied for static stress analysis, and the result of which is reviewed for compatability with applicable standard. As a result, sliding and overturning are not expected under design basis earthquakes for increased storage cases of 17 tray and 18 tray stacks. And it is anticipated the result of stress analysis will be acceptable.

2003-07-01

372

Seismic stability analysis of the spent fuel storage structures for increase of storage capacity at Wolsung NPP  

International Nuclear Information System (INIS)

This paper introduces the method of seismic stability analysis for the increase of fuel storage capacity of wet storage stacks by one or two more stack floor at Wolsung Nuclear Unit 2,3,4, which had been originally licensed assuming 16 tray stack-o-storage. As a basic procedure, tipping and sliding stability of the structure is checked at first thru seismic analysis and the resultant load from dynamic analysis is applied for static stress analysis, and the result of which is reviewed for compatability with applicable standard. As a result, sliding and overturning are not expected under design basis earthquakes for increased storage cases of 17 tray and 18 tray stacks. And it is anticipated the result of stress analysis will be acceptable.

2003-05-29

373

Report documents O M at pumped-storage plants  

Energy Technology Data Exchange (ETDEWEB)

The Electric Power Research Institute has published a report for planners, designers, owners, and operators of hydroelectric pumped-storage plants that records the operation and maintenance knowledge of 35 domestic and foreign pumped-storage projects. The report provides a comprehensive record of practices that have reduced forced outages and shortened scheduled repairs. As time passes and experienced staff retire at pumped-storage plants, many O M lessons are lost. To remedy that situation, EPRI commissioned Morrison-Knudsen Engineers Inc. to prepare a special report. The 348-page publication records the accumulated civil, geotechnical, mechanical, and electrical O M knowledge and experiences of pumped-storage plant staff. It also includes recommendations to planners and designers of future pumped-storage plants and concludes with descriptions of O M experiences reported by plant ...

1991-12-01

374

Waste Generation and Pollution Prevention Progress Fact Sheet: Oak Ridge National Laboratory  

Energy Technology Data Exchange (ETDEWEB)

This 2-page fact sheet gives statistics on routine waste generation and projected reduction by waste type, and 1994 pollution prevention and recycling accomplishments at ORNL.

1996-09-01

375

Regional assessment of nonforestry related biomass resources: South Carolina  

Energy Technology Data Exchange (ETDEWEB)

This document is a collection of spreadsheets detailing in a county by county manner the agricultural crop, agricultural wastes, municipal wastes, and industrial wastes of South Carolina that are potential biomass energy sources.

1988-11-01

376

Regional assessment of nonforestry related biomass resources: North Carolina  

Energy Technology Data Exchange (ETDEWEB)

This document is a collection of spreadsheets detailing in a county by county manner the agricultural crop, agricultural wastes, municipal wastes and industrial wastes of North Carolina that are potential biomass energy sources.

1988-11-01

377

Probabilities of a catastrophic waste hoist accident at the Waste Isolation Pilot Plant  

Energy Technology Data Exchange (ETDEWEB)

This report shows the probability of a catastrophic accident involving the WIPP waste hoist system. Calculations and mitigation to reduce the probability of an accident and to minimize the impact of such an accident should be included. 10 refs., 8 figs., 4 tabs.

1990-01-01

378

Oak Ridge National Laboratory Technology Logic Diagram. Volume 2, Technology Logic Diagram: Part C, Waste Management  

Energy Technology Data Exchange (ETDEWEB)

This report documents site remediation at ORNL, including ORNL site characterization technologies, waste management and robotics and automation of the laboratory for waste processing and analysis.

1993-09-01

379

ORNL nuclear waste programs annual progress report for period ending September 30, 1982  

Energy Technology Data Exchange (ETDEWEB)

Research progress is reported in 20 activities under the headings: spent fuels, defense waste management, commercial waste management, remedial action, and conventional reactors. Separate entries were prepared for each activity.

1983-05-01

380

Integrated Models for Solid Waste Management in Tourism Regions: Langkawi Island, Malaysia  

Science.gov (United States)

The population growth, changing consumption patterns, and rapid urbanization contribute significantly to the growing volumes of solid waste that are generated in urban settings. As the rate of urbanization increases, demand on the services of solid waste management increases. The rapid urban growth in Langkawi Island, Malaysia, combined with the increasing rates of solid waste production has provided evidence that the traditional solid waste management practices, particularly the methods of waste collection and disposal, are inefficient and quite nonsustainable. Accordingly, municipal managers and planners in Langkawi ...

2011-09-04

381

Fusion Reactor Radioactive Waste Management.  

Science.gov (United States)

Quantities and compositions of non-tritium radioactive waste are estimated for some current conceptual fusion reactor designs, and disposal of large amounts of radioactive waste appears necessary. Although the initial radioactivity of fusion reactor and f...

1976-01-01

382

Department of Energy low-level waste management strategy  

Energy Technology Data Exchange (ETDEWEB)

The DOE strategy recognizes that public perception of low-level waste management practices is not positive. Actions are included that are aimed at opening the system to the public. A better informed public will be able to better assess the performance of the low-level waste management system.

1980-01-01

383

Cumulative releases of radionuclides from uncontained waste packages  

Energy Technology Data Exchange (ETDEWEB)

This report describes mathematical predictions for the migration of radionuclides from an emplaced radioactive waste container. The model assumes a spherical-equivalent waste solid surrounded by backfill but neglects the effect of decay heat. 7 refs., 2 tabs. (TEM)

1986-07-01

384

Conditioning of plastic wastes for thermal utilization; Aufbereitung von Kunststoffabfaellen zur thermischen Verwertung  

Energy Technology Data Exchange (ETDEWEB)

This article describes the processes for the treatment of plastic waste: sampling, sorting, comminution. The requirements for the different processes for waste treatment (as recycling, utilization as raw material, energy recovery, combustion) are listed. (SR)

1996-12-31

385

Solidification of problem wastes: Annual progress report, October 1985-September 1986  

Energy Technology Data Exchange (ETDEWEB)

This report describes initial work on the development of solidification systems for sodium nitrate waste and compacted waste. Sodium nitrate waste has been solidified in three types of materials: polyethylene, polyester-styrene (PES), and latex cement. Evaluations of the properties of the waste form, such as the ANS 16.1 leaching test, water immersion test and compressive strength measurements were performed on the waste forms containing various amounts of sodium nitrate. 9 refs., 9 figs., 7 tabs.

1987-02-01

386

Hazardous waste operational plan for site 300  

Energy Technology Data Exchange (ETDEWEB)

This plan outlines the procedures and operations used at LLNL's Site 300 for the management of the hazardous waste generated. This waste consists primarily of depleted uranium (a by-product of U-235 enrichment), beryllium, small quantities of analytical chemicals, industrial type waste such as solvents, cleaning acids, photographic chemicals, etc., and explosives. This plan details the operations generating this waste, the proper handling of this material and the procedures used to treat or dispose of the hazardous waste. A considerable amount of information found in this plan was extracted from the Site 300 Safety and Operational Manual written by Site 300 Facility personnel and the Hazards Control Department.

1982-02-12

387

Hazardous waste and environmental trade: China`s issues  

Energy Technology Data Exchange (ETDEWEB)

By presenting some case studies, this paper analyzes China`s situation with regard to hazardous waste: its environmental trade, treatment, and management. The paper describes China`s experiences with the environmental trade of hazardous waste in both the internal and international market. Regulations for managing the import of waste are discussed, as are China`s major approaches to the trading of hazardous waste both at home and overseas. The major reasons for setting up the Asian-Pacific Regional Training Center for Technology Transfer and Environmental Sound Management of Wastes in China and the activities involved in this effort are also described. 1 tab.

1996-12-31

388

Development of the alcohol waste processing equipment  

International Nuclear Information System (INIS)

In the experimental fast Reactor JOYO, gripper of Fuel Handling Machine and Ex-Vessel Transfer Machine that the sodium adhered is being washed with alcohol. This radioactive alcohol waste that was used to the washing is stored to the tank. If it is able to separate the alcohol and sodium in the alcohol waste it becomes possible to dispose of the alcohol waste. Japan Nuclear Institute and Fuji Electric Systems CO., LTD. Developed the device that adds carbonic acid gas to the alcohol waste and cause the sodium in the alcohol waste separated as carbonate and remove this carbonate by using the thin film evaporator. (author)

2004-11-01

389

Waste reduction at the Savannah River Site  

Energy Technology Data Exchange (ETDEWEB)

The Savannah River Site (SRS) is a key installation for the production and research of nuclear materials for national defense and peace time applications and has been operating a full nuclear fuel cycle since the early 1950s. Wastes generated include high level radioactive, transuranic, low level radioactive, hazardous, mixed, sanitary, and aqueous wastes. Much progress has been made during the last several years to reduce these wastes including management systems, characterization, and technology programs. The reduction of wastes generated and the proper handling of the wastes have always been a part of the Site's operation. This paper summarizes the current status and future plans with respect to waste reduction to waste reduction and reviews some specific examples of successful activities.

1990-01-01

390

Waste reduction at the Savannah River Site  

Energy Technology Data Exchange (ETDEWEB)

The Savannah River Site (SRS) is a key installation for the production and research of nuclear materials for national defense and peace time applications and has been operating a full nuclear fuel cycle since the early 1950s. Wastes generated include high level radioactive, transuranic, low level radioactive, hazardous, mixed, sanitary, and aqueous wastes. Much progress has been made during the last several years to reduce these wastes including management systems, characterization, and technology programs. The reduction of wastes generated and the proper handling of the wastes have always been a part of the Site`s operation. This paper summarizes the current status and future plans with respect to waste reduction to waste reduction and reviews some specific examples of successful activities.

1990-12-31

391

Solid Waste & Financial Assistance Program  

Science.gov (United States)

This program deals with solid waste disposal with topics/services covering: Reusable Building Materials and Large Household Items Exchange, Beneficial Use Determination, Biosolids, Certification, Compost Facil...

392

SUCCESSES AND EMERGING ISSUES IN SIMULATING THE MIXING BEHAVIOR OF LIQUID-PARTICLE NUCLEAR WASTE SLURRIES AT THE SAVANNAH RIVER SITE - 211B  

Energy Technology Data Exchange (ETDEWEB)

Aqueous radioactive high-level waste slurries are combined during processing steps that ultimately produce a stable borosilicate glass waste form. Chemically treated waste slurries are combined with each other and with glass frit-water slurries to produce the melter feed. Understanding the evolution of the rheological properties of the slurries is an important aspect of removing and treating the stored waste. To a first approximation, combinations of colloidal waste slurry with {approx}0.1-mm mean diameter glass frit or glass beads act in an analogous matter to slurries of spherical beads in Newtonian liquids. The non-Newtonian rheological properties of the waste slurries without frit, however, add complexity to the hydrodynamic analysis. The use of shear rate dependent apparent viscosities with the modified Einstein equation was used to model the rheological ...

2009-09-02

393

Proceedings of the eighth annual DOE low-level waste management forum: Technical Session 6, Waste treatment  

Energy Technology Data Exchange (ETDEWEB)

Nine papers in this proceedings have been processed for inclusion in the Energy Data Base. (AT)

1987-02-01

394

Nuclear waste plans enter critical phase  

Energy Technology Data Exchange (ETDEWEB)

A brief article considers the possible result of the enquiry into Nirex`s plan to build an underground rock laboratory at Sellafield in relation to radioactive waste disposal in the UK. (UK).

1996-10-31

395

Nondestructive characterization of low-level transuranic waste  

Energy Technology Data Exchange (ETDEWEB)

The use of nondestructive evaluation (NDE) methods is proposed for characterization of transuranic (TRU) waste stored at the Radioactive Waste Management Complex. These NDE methods include real-time x-ray radiography, real-time neutron radiography, x-ray and neutron computed tomography, thermal imaging, container weighing, visual examination, and acoustic measurements. An integrated NDE system is proposed for characterization and certification of TRU waste destined for eventual shipment to the Waste Isolation Pilot Plant in New Mexico. Methods for automating both the classification waste and control of a complete nondestructive evaluation/nondestructive assay system are presented. Feasibility testing of the different NDE methods, including real-time x-ray radiography, and development of automated waste classification techniques are covered as part of a five year ...

1981-10-01

396

NASA - Waste Not  

Science.gov (United States)

Jun 4, 2004 ... On a two-year trip to Mars, according to one estimate, a crew of six humans will generate more than six tons of solid organic waste--much of ...

397

NAME=\\  

Wastenet

... Waste Collection Systems Products and Equipment Find and compare a variety of waste collection systems products and equipment on the world's largest environmental industry portal. View product ...

398

Mixed waste disposal facility at the Nevada Test Site  

Energy Technology Data Exchange (ETDEWEB)

This report provides a brief overview of the history and planning for a proposed mixed waste disposal site on the Nevada Test Site. 8 figs.

1987-01-01

399

Kraft pulping of industrial wood waste  

Science.gov (United States)

Jun 16, 2011 ... Description: Most of the approximately 25 to 30 million tons of industrial wood waste generated in the United States per year is burned for ...

400

Fish waste - NASA Quest  

Science.gov (United States)

Seriously, generally fish waste does drop, but quite slowly. But a good group of snails should still do a fine job of cleaning the tank. ...

401

Factoring Potential Accelerator Transmutation of Waste Demonstrations into Accelerator Production of Tritium Design Planning  

CERN Document Server

Factoring Potential Accelerator Transmutation of Waste Demonstrations into Accelerator Production of Tritium Design Planning

1998-01-01

402

Current waste-management practices and operations at Oak Ridge National Laboratory, 1982  

Energy Technology Data Exchange (ETDEWEB)

The need for efficient management of industrial chemical wastes, especially those considered hazardous or radioactive, is receiving increased attention in the United States. During the past five years, several federal laws have addressed the establishment of stronger programs for the control of hazardous and residual wastes. At a facility such as Oak Ridge National Laboratory (ORNL), an efficient waste management program is an absolute necessity to ensure protection of human health and compliance with regulatory requirements addressing the treatment and disposal of hazardous, nonhazardous, and radioactive wastes. This report highlights the major regulatory requirements under which the Laboratory must operate and their impact on ORNL facilities. Individual waste streams, estimates of quantities of waste, and current waste management ...

1982-09-01

403

Converting Simulated Sodium-bearing Waste into a Single Solid Waste Form by Evaporation: Laboratory- and Pilot-Scale Test Results on Recycling Evaporator Overheads  

Energy Technology Data Exchange (ETDEWEB)

Conversion of Idaho National Engineering and Environmental Laboratory radioactive sodium-bearing waste into a single solid waste form by evaporation was demonstrated in both flask-scale and pilot-scale agitated thin film evaporator tests. A sodium-bearing waste simulant was adjusted to represent an evaporator feed in which the acid from the distillate is concentrated, neutralized, and recycled back through the evaporator. The advantage to this flowsheet is that a single remote-handled transuranic waste form is produced in the evaporator bottoms without the generation of any low-level mixed secondary waste. However, use of a recycle flowsheet in sodium-bearing waste evaporation results in a 50% increase in remote-handled transuranic volume in comparison to a non-recycle flowsheet.

2004-01-01

404

Acid Waste Equipment on Environmental Expert  

Wastenet

...Systems by IPEX Enfield electrofusion acid waste systems give you the proven corrosion resistance of polypropylene, along with our patented, state-of-the-art electrofusion system....

405

Storage Reliability of Missile Materiel Program. Storage ...  

Science.gov (United States)

... 6.2-18 for Aluminum Electrolytic Capacitors (MIL-C- 39018, Style CU (Aluminum Oxide)) 6.2-14 MIL-HDBK-217B Operational Failure Rate Model ...

1976-05-01

406

Short rotation coppice: a guide to cold storage of planting material  

Energy Technology Data Exchange (ETDEWEB)

This guide has been written to introduce growers of Short Rotation Coppice (SRC) to the principles and need for cold storage of planting material. The main types of cold store are described. It also provides assistance in the selection of suitable stores and how these are located nationally. (author)

1999-07-01

407

Seal is successful at Italys largest pumped storage plant  

British Library Electronic Table of Contents (United Kingdom)

A HydroSele S seal from James Walker has provided more than two years maintenance-free service at the large Entracque pumped-storage hydroelectric scheme in Italy.

2008-01-01

408

Quality assurance requirements for packaging, shipping, receiving, storage, and handling of items for water-cooled nuclear power plants (Revision 1) - October 1976  

International Nuclear Information System (INIS)

This guide describes an acceptable method of complying with the Commission's regulations with regard to the quality assurance requirements for the packaging, shipping, receiving, storage, and handling of items for water-cooled nuclear power plants.

409

Proton storage ring (PSR) diagnostics and control system  

Energy Technology Data Exchange (ETDEWEB)

When any new accelerator or storage ring is built that advances the state of the art, the diagnostic system becomes extremely important in tuning the facility to full specification. This paper will discuss the various diagnostic devices planned or under construction for the PSR and their connection into the control system.

1983-01-01

410

Overall control and monitoring systems for pumped storage plants  

Energy Technology Data Exchange (ETDEWEB)

The article describes control and monitoring concepts in which the delegation of responsibility is becoming more decisive than ever (automation hierarchy), and which are capable of optimized, automatic control of process events in pumped storage plants. 8 refs.

1982-06-01

411

Nanotechnology broadly refers to phenomenon and ... - NASA  

Science.gov (United States)

Jul 16, 2005 ... The purpose of this capability portfolio is to develop a roadmap for NASA to exploit .... 1.2.4-2: Some applications of nanotechnology to advanced EVA suits. ..... Power/Energy Storage: Materials and devices for energy storage and .... to 80 %), manufacturing costs (up to 50%) and enhancements in durability. ...

412

Lesson 5: How Can You  

Wastenet

Pumped storage plants 20 are a relatively common type.They use a dam to create an upper reservoir ...Some pumped storage plants use the same water turbine and electric generator for both operating periods.That is,

413

Lesson 5: How Can You  

Wastenet

Pumped storage plants are a relatively common type.They use a dam to create an upper reservoir ...Some pumped storage plants use the same water turbine and electric generator for both operating periods.

414

Heat storage material  

Science.gov (United States)

The heat storage material consists of a mixture of oleic and stearic acids in which stearic acid is present to the extent of 30 percent to 90 percent by weight. In addition to this binary system, the invention is also directed to a ternary system in which diphenyl ether is present along with the stearic and oleic acids.

1955-12-06

415

EDF's experience in the operation of pump-storage plants  

Energy Technology Data Exchange (ETDEWEB)

This paper describes the advent of energy pumped storage plants in France, in connection with nuclear power reactors development and gives detailed specifications of different components (pump turbines, alternators, valves ...). 5 figs., 3 tabs.

1992-01-01

416

Duration of red blood cell storage is associated with increased incidence of deep vein thrombosis and in hospital mortality in patients with traumatic injuries  

UK PubMed Central (United Kingdom)

IntroductionIn critically ill patients the relationship between the storage age of red blood cells (RBCs) transfused and outcomes are controversial. To determine if duration of RBC...Full Text Available

2009-01-01

417

Association between length of storage of red blood cell units and outcome of critically ill children: a prospective observational study  

UK PubMed Central (United Kingdom)

IntroductionTransfusion is a common treatment in pediatric intensive care units (PICUs). Studies in adults suggest that prolonged storage of red blood cell units is associated with...Full Text Available

2010-01-01

418

A device for controlling the degree of discharge intensity of a storage battery  

Energy Technology Data Exchange (ETDEWEB)

The device is designed for automatic testing of the degree of discharge of tractive storage batteries (AB) for electric loaders, electric cars and electric ore locomotives. The basic electrical schematic of the device is cited.

1983-01-01

419

A Novel Mouse Model of Red Blood Cell Storage and Post-Transfusion in Vivo Survival  

UK PubMed Central (United Kingdom)

BackgroundStorage of RBCs is necessary for an adequate blood supply. However, reports have identified potential negative sequelae of transfusing stored RBCs. An animal...Full Text Available

2009-08-01

420

33 CFR 148.105 - What must I include in my application?  

Science.gov (United States)

...capacity, and ownership of all planned and existing onshore pipelines, storage facilities, refineries, petrochemical...will be served by the port, including: (i) Onshore pipelines; (ii) Storage facilities; (iii)...

2010-07-01

421

The impact of fatigue strength considerations for the lifetime management for pumped-storage power plants  

Energy Technology Data Exchange (ETDEWEB)

Due to changed operational conditions and because of the increasing age of several hydro power plant components, there is an increasing risk of damages and the control of degradation mechanisms is of increasing significance. Therefore lifetime considerations for safety relevant components in pumped-storage plants become more and more important. The development of a lifetime management system, in conjunction with monitoring systems and specific surveillance for a group of pumped-storage power plants of different ages and in a wide range of power output is presented. The special focus is on the impact of fatigue strength considerations within this framework. The applied procedure will be described for typical mechanical components in pumped-storage plants exemplarily. (orig.)

2010-07-01

422

Stress analysis of hydride bed vessels used for tritium storage  

Energy Technology Data Exchange (ETDEWEB)

A prototype hydride storage bed, using LaNi{sub 4.25}Al{sub 0.75} as the storage material, was fitted with strain gages to measure strains occurring in the stainless steel bed vessel caused by expansion of the storage powder upon uptake of hydrogen. The strain remained low in the bed as hydrogen was added, up to a bed loading of about 0.5 hydrogen to metal atom ratio (H/M). The strain then increased with increasing hydrogen loading ({approximately} 0.8 H/M). Different locations exhibited greatly different levels of maximum strain. In no case was the design stress of the vessel exceeded.

1991-01-01

424

Plasma treatment of polymer dielectric films to improve capacitive energy storage  

Science.gov (United States)

Demand for compact instrumentation, portable field equipment, and new electromagnetic weapons is

1994-01-01

425

Orbital storage and supply of subcritical liquid nitrogen  

Science.gov (United States)

Subcritical cryogenic fluid management has long been recognized as an enabling technology for key

1990-01-01

426

Nuclear power plants connected with pumped storage plants by the inland lakes  

International Nuclear Information System (INIS)

Finnish (May 1971). Finland Kilpelaeinen, JE Imatran Voima Osakeyhtio,

1971-01-01

427

New crafts of a master builder  

Energy Technology Data Exchange (ETDEWEB)

Innovative new ideas for the construction of homes are described. A thermal energy storage system fireplace and a geothermal heat pump for homes are described.

1983-11-01

428

National coordination of NPP operation: Belgian case  

International Nuclear Information System (INIS)

Adjusting generation to demand (load following) is compared with practical experience. The importance of pumped storage plants is emphasized.

1986-01-01

430

Hydroelectric Power Plants Electrical Design  

Science.gov (United States)

... Treatment of electrical systems for pumped storage plants is not covered in the manual, although much of the information is applicable to pumped ...

1994-06-30

433

Cryogenic liquid transfer termination apparatus  

International Nuclear Information System (INIS)

Apparatus for termination of cryogenic liquid transfer from a liquid supply container to a storage-dispensing container is disclosed.

434

CARBON DIOXIDE REDUCTION SYSTEM  

Science.gov (United States)

... be easily replaceable, and its compartment or container ... in a simple, efficient manner for storage or disposal. ... and enters the reactor at approximatel ...

1963-01-01

435

Borehole heat store design optimization. The SmartStore model  

Energy Technology Data Exchange (ETDEWEB)

The SmartStore model was developed to determine the optimum design of borehole heat stores as a function of different design parameters. The optimum design is defined as the design that achieves the storage task with a minimum annual storage cost. The annual storage cost is the sum of annual costs of investment, operation, maintenance and heat loss. The PC-model has a user-friendly lay-out and gives a fast pre-design of borehole heat stores. In this article the model is briefly described. It is also shown that the technical design of the store is influenced by varying technical properties of the storage volume, but also by the cost of heat. (orig.)

1994-12-31

436

A Generalized Simulation Model for Reservoir System ...  

Science.gov (United States)

... Hydropower analysis may include run-of-river, peaking, and pumped storage plants as well as system power operation. ...

1992-03-01

437

Review of high-level waste form properties. [146 bibliographies  

Energy Technology Data Exchange (ETDEWEB)

This report is a review of waste form options for the immobilization of high-level-liquid wastes from the nuclear fuel cycle. This review covers the status of international research and development on waste forms as of May 1979. Although the emphasis in this report is on waste form properties, process parameters are discussed where they may affect final waste form properties. A summary table is provided listing properties of various nuclear waste form options. It is concluded that proposed waste forms have properties falling within a relatively narrow range. In regard to crystalline versus glass waste forms, the conclusion is that either glass of crystalline materials can be shown to have some advantage when a single property is considered; however, at this date no single waste form offers optimum ...

1980-12-01

438

Utility battery storage systems program report for FY 94  

Energy Technology Data Exchange (ETDEWEB)

Sandia National Laboratories, New Mexico, conducts the Utility Battery Storage Systems Program, which is sponsored by the US Department of Energy`s Office of Energy Management. The goal of this program is to assist industry in developing cost-effective battery systems as a utility resource option by 2000. Sandia is responsible for the engineering analyses, contracted development, and testing of rechargeable batteries and systems for utility energy storage applications. This report details the technical achievements realized during fiscal year 1994.

1995-03-01

439

Utility Battery Storage Systems Program report for FY93  

Energy Technology Data Exchange (ETDEWEB)

Sandia National Laboratories, New Mexico, conducts the Utility Battery Storage Systems Program, which is sponsored by the US Department of Energy`s Office of Energy Management. In this capacity, Sandia is responsible for the engineering analyses, contract development, and testing of rechargeable batteries and systems for utility-energy-storage applications. This report details the technical achievements realized during fiscal year 1993.

1994-02-01

440

Project quality assurance plant: Sodium storage facility, project F-031  

International Nuclear Information System (INIS)

The Sodium Storage Facility Project Quality Assurance Plan delineates the quality assurance requirements for construction of a new facility, modifications to the sodium storage tanks, and tie-ins to the FFTF Plant. This plan provides direction for the types of verifications necessary to satisfy the functional requirements within the project scope and applicable regulatory requirements determined in the Project Functional Design Criteria (FDC), WHC-SD-FF-FDC-009.

441

Perspectives on energy storage wheels for space station application  

Energy Technology Data Exchange (ETDEWEB)

Several of the issues of the workshop are addressed from the perspective of a potential Space Station developer and energy wheel user. Systems considerations are emphasized rather than component technology. The potential of energy storage wheel (ESW) concept is discussed. The current status of the technology base is described. Justification for advanced technology development is also discussed. The study concludes that energy storage in wheels is an attractive concept for immediate technology development and future Space Station application.

1984-11-01

442

Overall control and monitoring systems for pumped storage plants  

Energy Technology Data Exchange (ETDEWEB)

Experience and technical innovations in power plant engineering have resulted in continuous improvements of operation control, availability and safety of pumped storage plants. Process control is constantly improved as new developments are made in equipment and systems engineering. Plant control concepts with increasingly complex automation hierarchy are described by which pumped storage processes can be controlled optimally, reliably, and automatically.

1982-01-01

443

Floating production and storage vessels - design analysis and operational issues: a handbook produced to accompany the Bentham Technical Training Courses  

Energy Technology Data Exchange (ETDEWEB)

These ten chapters present an overview of floating production, storage and offloading (FPSO) vessels, and examines deep water developments; hydrostatic stability; production, storage and offloading systems; the configuration and structure of flexible risers and umbilicals; the structural and global dynamic analysis of flexible riser and umbilicals; verification of FPSO structural integrity; vessel global loading and rigid body response; environmental loading and vessel response; and mooring systems. (UK)

1998-07-01

444

Energy storage capacitors  

Energy Technology Data Exchange (ETDEWEB)

The properties of capacitors are reviewed in general, including dielectrics, induced polarization, and permanent polarization. Then capacitance characteristics are discussed and modelled. These include temperature range, voltage, equivalent series resistance, capacitive reactance, impedance, dissipation factor, humidity and frequency effects, storage temperature and time, and lifetime. Applications of energy storage capacitors are then discussed. (LEW)

1984-01-01

445

ENERGY EFFICIENCY AND ENVIRONMENTALLY FRIENDLY DISTRIBUTED ENERGY STORAGE BATTERY  

Energy Technology Data Exchange (ETDEWEB)

Electro Energy, Inc. conducted a research project to develop an energy efficient and environmentally friendly bipolar Ni-MH battery for distributed energy storage applications. Rechargeable batteries with long life and low cost potentially play a significant role by reducing electricity cost and pollution. A rechargeable battery functions as a reservoir for storage for electrical energy, carries energy for portable applications, or can provide peaking energy when a demand for electrical power exceeds primary generating capabilities.

2006-04-30

446

Commodity storage valuation: A linear optimization based on traded instruments  

British Library Electronic Table of Contents (United Kingdom)

A valuation methodology for commodity storage facilities is proposed. This model utilizes traded instruments to replicate the fundamental derivative components of commodity storage facilities. The methodology is robust to different commodities, physical characteristics, and markets for valuing these types of assets. Two examples using the U. S. natural gas markets are presented.

2006-01-01

448

Waste Diversion | Greening EPA | US EPA  

Wastenet

...diversion generates a host of environmental, financial, and social benefits, including conserving energy, reducing disposal costs, and reducing the burden on landfills and other waste disposal methods . Waste Diversion at EPA For many years, EPA has established waste diversion goals that exceed current federal requirements. EPA ...

449

Utilization of plastic wastes in a blast furnace - a contribution to ecological and economical recycling of plastic wastes; Kunststoffverwertung im Hochofen - ein Beitrag zum oekologischen und oekonomischen Recycling von Altkunststoffen  

Energy Technology Data Exchange (ETDEWEB)

This article describes the utilization of plastic wastes in a blast furnace. The plastic waste is a substitution for petroleum and coal as a raw material for synthesis gas production. The synthesis gas is the reducing agent in the blast furnace for the reduction of iron ores. You can find here an ecological and economical analysis of this process in comparison to the utilization of petroleum and coal. (SR)

1996-12-31

453

Resources | Environment Knowledge Hub  

Wastenet

... MUNICIPAL SOLID WASTES (MANAGEMENT AND HANDLING) RULES, 2000 Plastic Bag ban in Dhaka City, Bangladesh Private Sector Participation in Municipal Solid Waste Management SKAT 2000 TECHNICAL GUIDELINES ON MUNICIPAL SOLID WASTE MANAGEMENT Hazardous Waste Management Unit, Environmental Pollution Control Division, Central Environmental Authority, Sri Lanka 2004 Subregional ...

454

Request for interim approval to operate 218-E-12B Trench 94 as a chemical waste landfill for disposal of polychlorinated biphenyl wastes in submarine reactor compartments. Revision 1.  

Science.gov (United States)

This request is submitted to seek interim approval to operate a chemical waste landfill for the disposal of polychlorinated biphenyl (PCB) waste. Interim approval is requested for a period not to exceed 5 years. This request covers only the disposal of sm...

1992-01-01

459

Oil refinery waste disposal methods, quantities and costs, 1993 survey  

Energy Technology Data Exchange (ETDEWEB)

This report summarizes the information gathered by CONCAVE in a 1993 survey of waste generation and disposal by the oil refineries in Western Europe. The survey covered the types of waste produced, their quantities, disposal routes and costs of disposal. The results are compared with those from a 1986 survey, but because of the increased numbers of refineries reporting, comparison is difficult. The survey revealed wide variations in disposal costs depending on waste type and local circumstances.

1995-06-01

461

Model analysis of an inter-industrial and inter-regional waste recycling system in Japan  

Energy Technology Data Exchange (ETDEWEB)

In this study, we investigate an inter-industrial and inter-regional recycling system for industrial waste by the cement industry in Japan. We develop a linear programming model that represents cement production processes and waste transportation of all cement factories in Japan. We simulate cost and CO{sub 2}-minimizing systems. The result implies that making waste transportation more efficient in cost is an effective means for CO{sub 2} reduction. (author)

2007-04-15

462

Methane fermentation of agricultural wastes and domestic animal's wastes  

Energy Technology Data Exchange (ETDEWEB)

Cattle and pig wastes, orange peels, compost, and grain husks were hydrolyzed in an alkaline medium to investigate the CH4 generation capacity. The respective CH4 production capacities from pig wastes and rice hulls were approximately 1 and approximately 0.1 L/g. The CH4 produced can be used to supplement energy requirements of farms.

1981-01-01

468

Idaho National Engineering Laboratory Nonradiological Waste Management Information for 1992 and record to date  

Energy Technology Data Exchange (ETDEWEB)

This document provides detailed data and graphics on airborne and liquid effluent releases, fuel oil and coal consumption, water usage, and hazardous and mixed waste generated for calendar year 1992. This report summarizes industrial waste data records compiled since 1971 for the Idaho National Engineering Laboratory (INEL). The data presented are from the INEL Nonradiological Waste Management Information System.

1993-08-01

469

GS1 - radiological protection objectives for the disposal of solid radioactive wastes  

Energy Technology Data Exchange (ETDEWEB)

A summary is given of the 1983 NRPB-GS1 Report on the 'Radiological protection objectives for the disposal of solid radioactive wastes'. The two principal difficulties in applying the ICRP system of dose limitation to some solid waste disposal methods are outlined. Despite these difficulties three radiological protection objectives for waste disposal were recommended based on the same fundamental principle as ICRP recommendations.

1984-01-01

470

Estimation of animal and olive solid wastes in Jordan and their potential as a supplementary energy source: An overview  

Energy Technology Data Exchange (ETDEWEB)

Biomass is a potential source of energy that can reduce our dependency on oil as the main source of energy. In addition to municipal solid waste, animal and olive wastes are the main sources of organic waste in Jordan. In 2005, there were more than 2.4 million heads of sheep, about 72 thousand cows, and 40 million hens being raised in farms distributed in all governorates of Jordan. These animals produce 5.3 million tons (as exerted) of solid waste per year. If these quantities can be effectively collected they may constitute a valuable source of energy. This paper is aiming to estimate the amounts of animal and solid wastes generated in Jordan and their energy potential. The total amount of BOD from animal waste is estimated at 200,000 tons per year. Significant quantities of organic waste can also be collected from olive mills distributed ...

2010-10-15

471

Environmental assessment of coal waste mounds in Japan using remote sensing techniques  

Energy Technology Data Exchange (ETDEWEB)

Focuses on the application of remote sensing techniques to the study of coal waste mounds. The situation at the coal waste mounds in Fukuoka, Japan is cited. Guidelines on film parameters, photographic keys and tasks required to inventory, monitor and manage coal waste mounds in Japan are addressed. Application of photogrammetry, remote sensing, aerial photography and satellite imagery techniques in monitoring spoil banks is reviewed. Applicability of the techniques is discussed. 24 refs.

1993-01-01

472

Energy recovery from waste by use of fluidized-bed technology  

Energy Technology Data Exchange (ETDEWEB)

Revolving type fluidized-bed technology, developed by Ebara Corp., is installed in more than 100 facilities worldwide. The technology is applied for waste, coal and in situations where a conventional fluidized bed is difficult to use. Waste and/or coal can be treated and valuable energy can be recovered from a non-renewable source. This paper describes the application of the revolving fluidized bed for waste, coal and tyres.

1999-07-01

473

EVALUATION OF RISKS AND WASTE CHARACTERIZATION REQUIREMENTS FOR THE TRANSURANIC WASTE EMPLACED IN WIPP DURING 1999  

Energy Technology Data Exchange (ETDEWEB)

Specifically this report: 1. Compares requirements of the WAP that are pertinent from a technical viewpoint with the WIPP pre-Permit waste characterization program, 2. Presents the results of a risk analysis of the currently emplaced wastes. Expected and bounding risks from routine operations and possible accidents are evaluated; and 3. Provides conclusions and recommendations.

2000-05-01

475

Decommissioning of facility for use of radioisotopes on waste management and disposal facility  

Energy Technology Data Exchange (ETDEWEB)

All the tests have been finished up in the Waste Management and Disposal Facility which has been used for the safety tests of solidified radioactive waste on sea dumping disposal. The decommissioning of this facility was performed for use of radioisotopes. This report describes the plan on decommissioning of facility for use of radioisotopes, the contamination checking methods and measurement of radioactivity, the fore case and practice for amount of generated radioactive wastes, the operation procedures for dismantlement, the safety measures, the expenses for decommissioning and so on. (author)

1999-09-01

477

Characterisation of long-lived low and intermediate-level radioactive wastes in the Nordic Countries  

International Nuclear Information System (INIS)

The present report is final report from a study on characterisation of radioactive waters in the Nordic countries. The study has mainly been focused on long-lived low and intermediate level radioactive waste. Methods to measure or estimate the activity content and the general composition are discussed. Recommendations are given regarding characterisation of waste under treatment and characterisation of already produced waste packages. (au).

2005-01-01

478

BC  

Wastenet

criteria which would constitute environmentally sound management of mobile phone waste in accordance with the Basel Convention;

479

BC  

Wastenet

all Certified ESM facilities capable of receiving used mobile phone waste from non-Annex VII countries.

480

Achievements and Perspectives of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management  

International Nuclear Information System (INIS)

The Joint Convention on the Safety of Spent Fuel management and on the Safety of Radioactive Waste Management is the first legal instrument to directly address the safety of spent fuel and radioactive waste management on a global scale. The Joint Convention entered into force in 2001. This paper describes its process and its main achievements to date. The perspectives to establish of a Global Waste Safety Regime based on the Joint Convention are also discussed. (authors)

482

Solar thermophotovoltaic (STPV) system with thermal energy storage  

Energy Technology Data Exchange (ETDEWEB)

A solar thermophotovoltaic (STPV) system has both terrestrial and space applications because thermal energy storage can be utilized. Excellent properties (heat of fusion=1800 j/gm and melting temperature=1680 K) make silicon the ideal thermal storage material for an STPV system. Using a one dimensional model with tapering of the silicon storage material, it was found that several hours of running time with modest lengths ({approximately}15 cm) of silicon are possible. Calculated steady-state efficiencies for an STPV system using an Er-YAG selective emitter and ideal photovoltaic (PV) cell model are in the range of 15{percent}{endash}17{percent}. Increasing the taper of the storage material improves both efficiency and power output. {copyright} {ital 1996 American Institute of Physics.}

1996-02-01

483

Risk trade-off linked to temporary storage function in road transports  

British Library Electronic Table of Contents (United Kingdom)

Today?s demand on high supply chain performance requires higher awareness about supply chain risks and uncertainty. The purpose of this paper is to analyse the role of temporary storage in the transport network in a supply chain perspective. The primary research question concerns the purpose or role of temporary storage and whether management of temporary storage can contribute to reducing risks and uncertainty in the supply chain. The research is based on a system-theoretical approach, which emphasizes a holistic view instead of the characteristics of the different parts. The research method used in this paper is abductive. Existing theories are used to formulate a framework which leads to a conceptual model description of the temporary storage function. This model is then supported and v...

2011-01-01

484

PSPs at Bhira and Bhivpuri  

International Nuclear Information System (INIS)

Tata Electric Companies (TEC) are engaged in the generation of hydro and thermal energy. TEC, to minimise backing down of its thermal units in off peak hours and also to at least partially meet the growing deficit in the supply during peak hours is moving to install pumped storage plants (PSPs) utilising off-peak surplus energy for pumping the water from lower pond to the upper pond for subsequent utilisation for power generation during peak hours. In view of some of the infra structural facilities such as storage ponds, water conductor system, transmission lines, etc. being already available, at the existing hydro power stations owned by TEC, the pumped storage units are being proposed within the environs of existing hydro stations, i.e. a 150 MW pumped storage unit at Bhira and a 90 MW pumped storage unit at Bhivpuri. The projects are described and cost estimates is given. ...

1992-01-01

485

Demonstration drop test and design enhancement of the CANDU spent fuel storage basket in dry storage facility  

British Library Electronic Table of Contents (United Kingdom)

A dry interim storage facility has been constructed at the Wolsung power plant in Korea. This dry storage facility has seven separated modules. There are 40 long slender cylinders in one module. In one cylinder, ten baskets where sixty CANDU spent fuel bundles are loaded are stacked and stored. For this dry storage facility, analyses and tests for hypothetical accident conditions that might occur while moving and storing the baskets into a cylinder were performed. In a demonstration test, one of test basket models did not satisfy one of the safety-related requirements. Thus, the revised basket designs were generated using a structural evaluation based on finite element analyses and specimen tests. Among these revised designs, one design was chosen as a final revised basket design. The fina...

2011-01-01

486

Bidding strategy for pumped-storage plant in pool-based electricity market  

Energy Technology Data Exchange (ETDEWEB)

This paper develops optimal bidding strategies for a pumped-storage plant in a pool-based electricity market. In the competitive regime, when compared to simple hydroelectric generator, profit of the pumped-storage plant is maximized by operating it as a generator when market clearing price is high and as a pump when the price is low. Based on forecasted hourly market clearing price, a multistage looping algorithm to maximize the profit of a pumped-storage plant is developed, considering both the spinning and non-spinning reserve bids and meeting the technical operating constraints of the plant. The proposed model is adaptive for the nonlinear three-dimensional relationship between the power produced, the energy stored, and the head of the associated reservoir. Different operating cycles for a realistic pumped-storage plant are considered and simulation results are reported and compared. (author)

2010-03-15

487

Assessment of radiological safety of Wolsung site at site boundary considering crack impact  

British Library Electronic Table of Contents (United Kingdom)

The number of spent fuel storage facilities in the world continues to increase because of "Wait and See" policies and delay of a permanent disposal plan. The temporary spent fuel storage concept is changing to a pre-disposal storage concept. Strengthened safety concepts are required for expanded spent fuel storage facilities and sites. The Korea Hydro and Nuclear Power Company is planning to construct a reinforced concrete MACSTOR-400 facility at Wolsung. In concrete dry spent fuel storage structures, cracks can occur due to radiant heat and environmental chloride. The likelihood of cracking increases over time. Research on changes in shielding performance from one collinear crack in the surface of a concrete facility has been carried out. However there is no research about public radiolog...

2010-01-01

488

A VRLA battery energy storage system for Metlakatla, Alaska  

Energy Technology Data Exchange (ETDEWEB)

The emergence of new power electronics and improved battery technology has created renewed interest in Battery Energy Storage Systems (BESS). These new systems provide electric utilities with alternatives to conventional storage technologies, such as pumped hydro. BESs has the potential to provide substantial benefits in terms of energy management, improved voltage, spinning reserve and protection from interruptions when compared to large centralized storage. This paper describes a commercial, economically justified, application of the new Battery Energy Storage Systems which is presently under construction in the Metlakatla Power and Light system. The paper outlines the system performance requirements which lead to consideration of BESS as an option; the economic factors which provided the justification for BESS as an economic alternative; and the overall BES system design and performance.

1996-11-01

489

Negotiating equity for management of DOE wastes  

Energy Technology Data Exchange (ETDEWEB)

One important factor frustrating optimal management of Department of Energy (DOE)-complex wastes is the inability to use licensed and permitted facilities systematically. Achieving the goal of optimal use of DOE`s waste management facilities is politically problematic for two reasons. First, no locale wants to bear a disproportionate burden from DOE wastes. Second, the burden imposed by additional wastes transported from one site to another is difficult to characterize. To develop a viable framework for equitably distributing these burdens while achieving efficient use of all DOE waste management facilities, several implementation and equity issues must be addressed and resolved. This paper discusses stakeholder and equity issues and proposes a framework for joint research and action that could facilitate equity negotiations among stakeholder and move toward a more optimal use of ...

1994-09-01

490

Low-level Waste Forum meeting report. Winter meeting, January 26--28, 1994  

Energy Technology Data Exchange (ETDEWEB)

The Low-Level Radioactive Waste Forum is an association of representatives of states and compacts established to facilitate state and compact commission implementation of the Low-Level Radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy Amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The Forum provides an opportunity for states and compacts to share information with one another and to exchange views with officials of federal agencies. The Forum participants include representatives from regional compacts, designated host states, unaffiliated states, and states with currently-operating low-level radioactive waste facilities. This report contains information synthesizing the accomplishments of the Forum, as well as any new advances that have been made in the management of low-level radioactive ...

1994-12-31

491

Liquid radioactive waste discharges from B plant to cribs  

Energy Technology Data Exchange (ETDEWEB)

This engineering report compiles information on types and quantities of liquid waste discharged from B-Plant directly to cribs, ditches, reverse wells, etc., that are associated with B-Plant. Waste discharges to these cribs via overflow form 241-B, 241-BX, and 241-BY tank farms, and waste discharged to these cribs from sources other than B-Plant are discussed.Discharges from B-Plant to other cribs, unplanned releases, or waste remaining in tanks are not included in the report. Waste stream composition information is used to predict quantities of individual chemicals sent to cribs. This provides an accurate mass balance of waste streams from B-Plant to these cribs. These predictions are compared with known crib inventories as a verification of the process.

1996-05-29

492

Theory and evidence of economies of scale in the development of waste management systems  

Energy Technology Data Exchange (ETDEWEB)

Waste is a cost of doing business. This cost can be considered in terms of the potential adverse health and environmental impacts, or the waste management costs associated with avoiding, minimizing, and controlling those impacts. There is an anticipated increase in the cost of waste management as a result of the increasing requirements for regulatory compliance. To meet the total waste management capacity needs of the organization and the compliance requirements, low-level radioactive, hazardous, and mixed waste management will need demonstrated technologies strategically managed as a technology portfolio. The role of the decision maker is to select the optimum mix of technologies and facilities to provide the waste management capacity needed for the next twenty years. The waste management system resulting from this mix includes multiple ...

1989-01-01

493

Analysis of options for coal combustion waste management in the Pacific Basin  

Energy Technology Data Exchange (ETDEWEB)

Many Pacific Basin countries rely on oil for electricity production. Alternative fuel sources such as coal, which is available in the Pacific Basin, can help mitigate adverse impacts of sudden price increases or supply disruptions. Coal combustion produces solid and potentially hazardous wastes of concern to environmental regulators and utility managers. This paper identifies issues associated with managing coal combustion wastes in the Pacific Basin, using the state of Hawaii as a case study. Hawaii is typical of many Pacific Basin locations in that it depends on oil, has limited sites, for waste management operations, and is subject to domestic and international waste management regulations. The paper discusses coal-fired utility wastes, environmental impacts of coal combustion waste disposal, and regulatory requirements that impact coal ...

1993-10-01