Heat Cycle Reserch Experimental Program report, FY-84
Energy Technology Data Exchange (ETDEWEB)
The Heat Cycle Research Facility (HCRF) is an experimental binary-cycle facility used to investigate different concepts and/or components for generating electrical power from a geothermal resource. This report briefly desc
1984-09-01
FY05-FY06 Advanced Simulation and Computing Implementation Plan, Volume 2
Energy Technology Data Exchange (ETDEWEB)
The Stockpile Stewardship Program (SSP) is a single, highly integrated technical program for maintaining the safety and reliability of the U.S. nuclear stockpile. The SSP uses past nuclear test data along with future non-nuclear test data, computational modeling and simulation, and experimental facilities to advance understanding of nuclear weapons. It includes stockpile surveillance, experimental research, development and engineering programs, and an appropriately scaled production capability to support stockpile requirements. This integrated national program will require the continued use of current facilities and programs along with new experimental facilities and computational enhancements to support these programs. The Advanced ...
2004-07-19
Fast reactor fuel pin performance requirements for off-normal events
International Nuclear Information System (INIS)
HEDL is conducting an experimental transient testing program to evaluate the performance of prototypic Fast Flux Test Facility (FFTF) fuel pins up to the cladding integrity limit. The relationship is described of the HEDL/TREAT transient overpower test program to the confirmation of FFTF fuel pin design bases via the FFTF fuel pin design procedure.
The U.S. Liquid Metal Reactor Development Program
International Nuclear Information System (INIS)
This paper discusses how the U.S. Liquid Metal Reactor Development Program has been restructured to carry out R and D on advanced reactor technology. The program gives particular emphasis to improvements to reactor safety. The new directions are based on the technology of the integral fast reactor (IFR). Much of the basis for superior safety performance using IFR technology has been experimentally verified and aggressive programs continue in EBR-II and TREAT. Progress has been made in demonstrating both the metallic fuel and the new electrochemical processes of the IFR. The FFTF facility is converting to metallic fuel; however, FFTF also maintains a considerable U.S. program in oxide fuels. In addition, generic programs are continuing in steam generator testing, materials development, and with international cooperation, aqueous reprocessing.
1988-05-01
United States Department of Energy breeder reactor staff training domestic program
Energy Technology Data Exchange (ETDEWEB)
Two US DOE projects in the Pacific Northwest offer unique on-the-scene training opportunities at sodium-cooled fast-reactor plants: the Fast Flux Test Facility (FFTF) near Richland, Washington, which has operated successfully in a wide range of irradiation test programs since 1980; and the Experimental Breeder Reactor II (EBR-II) near Idaho Falls, Idaho, which has been in operation for approximately 20 years. Training programs have been especially designed to take advantage of this plant experience. Available courses are described.
1984-01-01
CFD investigation of balcony spill plumes in atria (part II)
Energy Technology Data Exchange (ETDEWEB)
This paper proposes an integrated method for using experimental data and CFD modeling to develop engineering correlations for atrium smoke management. Part I focused on the experimental program and validation of a CFD model of the experimental facility. Part II describes the extension of this model to a parametric study of balcony spill plumes. Smoke management in buildings during fire events often uses mechanical ventilation systems to maintain smoke layer elevation above a safe evacuation path. Design of these systems requires accurate correlations for the smoke production or mass flow rate of the buoyant fire plume. One design issue is the mass flow rate of fire plumes which spill out from a fire compartment, under a balcony and up through an atrium or other large volume. Current engineering correlations for these balcony spill plumes (BSPs) are based on a combination of ...
2005-07-01
CFD investigation of balcony spill plumes in atria (part II)
International Nuclear Information System (INIS)
This paper proposes an integrated method for using experimental data and CFD modeling to develop engineering correlations for atrium smoke management. Part I focused on the experimental program and validation of a CFD model of the experimental facility. Part II describes the extension of this model to a parametric study of balcony spill plumes. Smoke management in buildings during fire events often uses mechanical ventilation systems to maintain smoke layer elevation above a safe evacuation path. Design of these systems requires accurate correlations for the smoke production or mass flow rate of the buoyant fire plume. One design issue is the mass flow rate of fire plumes which spill out from a fire compartment, under a balcony and up through an atrium or other large volume. Current engineering correlations for these balcony spill plumes (BSPs) are based on a combination of ...
Data report of BWR post-CHF tests. Transient core thermal-hydraulic test program. Contract research
Energy Technology Data Exchange (ETDEWEB)
JAERI has been performing transient core thermal-hydraulic test program. In the program, authors performed BWR/ABWR DBE simulation tests with a test facility, which can simulate BWR/ABWR transients. The test facility has a 4 x 4 bundle core simulator with 15-rod heaters and one non-heated rod. Through the tests, authors quantified the thermal safety margin for core cooling. In order to quantify the thermal safety margin, authors collected experimental data on post-CHF. The data are essential for the evaluation of clad temperature transient when core heat-up occurs during DBEs. In comparison with previous post-CHF tests, present experiments were performed in much wider experimental condition, covering high clad temperature, low to high pressure and low to high mass flux. Further, data at wider elevation (lower to higher elevation of core) were obtained in the ...
2001-03-01
Development of LMFBR safety testing in FFTF
International Nuclear Information System (INIS)
The Fast Flux Test Facility (FFTF) will provide a prototypic test environment for advanced fuels and materials development within the U. S. LMFBR program. As a fast test reactor, the FFTF also provides a potentially unique capability for conduct of safety experimentation relevant to selected LMFBR safety issues associated with postulated core disruption events. The utility and feasibility of possible extension of FFTF testing into the area of safety research is being investigated. 5 fig.
1976-10-01
Energy Engineering Analysis Program (EEAP), Cornhusker ...
... is to develop a systematic program of energy consumption reductions in compliance with the stated goals of the Army Facilities Energy Plan (AFEP ...
1984-03-01
The ALPHA programs and thermal-hydraulic facilities at PSI
International Nuclear Information System (INIS)
... J. DREIER, M. HUGGENBERGER, C. AUBERT, TH BANDURSKI, F. DE
1999-12-01
Development of a Standard Data Base and Computer ...
... (Author). Descriptors : (*TERMINAL FLIGHT FACILITIES ... PROGRAMMING, HANDLING), QUEUEING THEORY, STOCHASTIC PROCESSES ...
1973-01-01
Advanced Simulation and Computing FY10-FY11 Implementation Plan Volume 2, Rev. 0.5
Energy Technology Data Exchange (ETDEWEB)
The Stockpile Stewardship Program (SSP) is a single, highly integrated technical program for maintaining the surety and reliability of the U.S. nuclear stockpile. The SSP uses past nuclear test data along with current and future non-nuclear test data, computational modeling and simulation, and experimental facilities to advance understanding of nuclear weapons. It includes stockpile surveillance, experimental research, development and engineering (D&E) programs, and an appropriately scaled production capability to support stockpile requirements. This integrated national program requires the continued use of current facilities and programs along with new experimental facilities and computational enhancements to support these ...
2009-09-08
Advanced Simulation & Computing FY09-FY10 Implementation Plan Volume 2, Rev. 0
Energy Technology Data Exchange (ETDEWEB)
The Stockpile Stewardship Program (SSP) is a single, highly integrated technical program for maintaining the safety and reliability of the U.S. nuclear stockpile. The SSP uses past nuclear test data along with current and future nonnuclear test data, computational modeling and simulation, and experimental facilities to advance understanding of nuclear weapons. It includes stockpile surveillance, experimental research, development and engineering programs, and an appropriately scaled production capability to support stockpile requirements. This integrated national program requires the continued use of current facilities and programs along with new experimental facilities and computational enhancements to support these programs. The ...
2008-04-30
SP-100 fuel pin performance: Results from irradiation testing
Energy Technology Data Exchange (ETDEWEB)
A total of 86 experimental fuel pins with various fuel, liner, and cladding candidate materials have been irradiated in the Experimental Breeder Reactor-II (EBR-II) and the Fast Flux Test Facility (FFTF) reactor as part of the SP-100 fuel pin irradiation testing program. Postirradiation examination results from these fuel pin are key in establishing performance correlations and demonstrating the lifetime and safety of the reactor fuel system. This paper provides a brief description of the in-reactor fuel pin tests and presents the most recent irradiation data on the performance of wrought rhenium (Re) liner material and high density UN fuel at goal burnup of 6 atom percent (at. %). It also provides an overview of the significant variety of other fuel/liner/cladding combinations which were irradiated as part of this program and which may be of interest to more advanced efforts.
1993-09-01
International Nuclear Information System (INIS)
The united research plan named 'Boiling' is created on the basis of several cryogenic research projects developed by experts in Russia and Ukraine for International Space Station. The 'Boiling' plan includes 8 first experiments aimed at investigating the influence of microgravity on boiling processes, heat transfer and hydrodynamics in liquid helium being either under normal or superfluid conditions. The experiments are supposed to be carried out with individual cells collected inside a single cryogenic onboard experimental facility. The international research program experiments are characterized by the following features: utilization of several artificially simulated microgravity levels, owing to rotation of the experimental helium cryostat; visualization of the processes that occur in liquid helium; research of boiling and hydrodynamics both in a large volume of stationary liquid, and in a liquid ...
2003-06-01
Laboratory directed research and development program, FY 1996
Energy Technology Data Exchange (ETDEWEB)
The Ernest Orlando Lawrence Berkeley National Laboratory (Berkeley Lab) Laboratory Directed Research and Development Program FY 1996 report is compiled from annual reports submitted by principal investigators following the close of the fiscal year. This report describes the projects supported and summarizes their accomplishments. It constitutes a part of the Laboratory Directed Research and Development (LDRD) program planning and documentation process that includes an annual planning cycle, projection selection, implementation, and review. The Berkeley Lab LDRD program is a critical tool for directing the Laboratory`s forefront scientific research capabilities toward vital, excellent, and emerging scientific challenges. The program provides the resources for Berkeley Lab scientists to make rapid and significant contributions to critical national science and technology problems. The LDRD ...
1997-02-01
Numerical simulation of slagging films in the Aachen pressurized coal combustion facility
Energy Technology Data Exchange (ETDEWEB)
Combined gas and steam turbine processes based on direct coal firing show a high thermal efficiency. At RWTH Aachen, University of Technology, an experimental test furnace has been built to investigate the pressurized pulverized coal combustion (PPCC). The PPCC-facility has been constructed as a slag tap furnace. Particles hitting the walls at temperatures above the melting point cause slagging depositions and create a film flowing down the reactor walls. As a part of the PPCC-program different mathematical models have been developed and implemented into the CFD-code FLUENT to predict the behavior of slag films at the furnace walls. Numerical strategies and the mathematical models used are described in detail. 12 refs., 9 figs.
2001-07-01
The cascad spent fuel dry storage facility
International Nuclear Information System (INIS)
France has a wide variety of experimental spent fuels different from LWR spent fuel discharged from commercial reactors. Reprocessing such fuels would thus require the development and construction of special facilities. The French Atomic Energy Commission (CEA) has consequently opted for long-term interim storage of these spent fuels over a period of 50 years. Comparative studies of different storage concepts have been conducted on the basis of safety (mainly containment barriers and cooling), economic, modular design and operating flexibility criteria. These studies have shown that dry storage in a concrete vault cooled by natural convection is the best solution. A research and development program including theoretical investigations and mock-up tests confirmed the feasibility of cooling by natural convection and the validity of design rules applied for fuel storage. A facility called CASCAD was built ...
1991-04-14
Solid Waste & Financial Assistance Program
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...
Federal Energy Management Program: Interagency Coordination
Program Plans, Implementation, & Results Energy Management at Federal Facilities Energy Management at DOE Fleet Management Interagency Coordination Interagency Energy...
2011-08-21
Liquid metal reactor cover gas purification and analysis in the USA
International Nuclear Information System (INIS)
Two sodium cooled reactors are currently being operated in the United States of America for the US Department of Energy. These are Experimental Breeder Reactor 11, EBR-11, and the Fast Flux Test Facility, FFTF. EBR-11 is located near Idaho Falls, Idaho, and the FFTF is near Richland, Washington. These reactors are currently engaged in a wide range of testing including fuels and materials tests, and plant system performance and safety development. The US DOE program also includes designs of a next generation sodium cooled power reactor. The FFTF and EBR-11 communities are providing input to these designs. This paper discusses the efforts to develop and operate cover gas systems for the sodium cooled nuclear reactor program in the USA.
1986-09-24
EBIT - Electronic Beam Ion Trap: N Divison experimental physics annual report 1995
Energy Technology Data Exchange (ETDEWEB)
The multi-faceted research effort of the EBIT (Electron Beam Ion Trap) program in N-Division of the Physics and Space Technology Department at Lawrence Livermore National Laboratory (LLNL) continues to contribute significant results to the physical sciences from studies with low energy very highly charged heavy ions. The EBIT program attracts a number of collaborators from the US and abroad for the different projects. The collaborations are partly carried out through participating graduate students demonstrating the excellent educational capabilities at the LLNL EBIT facilities. Moreover, participants from Historically Black Colleges and Universities are engaged in the EBIT project. This report describes EBIT work for 1995 in atomic structure measurements and radiative transition probabilities, spectral diagnostics for laboratory and astrophysical plasmas, ion/surface interaction studies, electron-ion interactions studies, ...
1996-10-01
This volume is a summary of the results of the final report of the Energy Engineering Analysis Program (EEAP) Study of 30 selected dining facilities at Fort Campbell, Kentucky.
1986-08-01
Research program: the investigation of heat transfer and fluid flow at low pressure
International Nuclear Information System (INIS)
This paper gives an overview of a multiyear joint research program being conducted at the University of New Mexico (UNM) with support from Sandia National Laboratories and GA Technologies. This research focuses on heat removal and fluid dynamics in flow regimes characterized by low pressure and low Reynolds number. The program was motivated by a desire to characterize and analyze cooling in a broad class of TRIGA-type reactors under: (a) typical operating conditions, (b) anticipated, new operating regimes, and (c) postulated accident conditions. It has also provided experimental verification of analytical tools used in design analysis. The paper includes descriptions of the UNM thermal-hydraulics test facility and the experimental test sections. During the first two years experiments were conducted using single, electrically heated rod in water and air annuli. This configuration ...
1986-04-07
Energy Engineering Analysis (EEA) Program, Europe. ...
... projects that will result in the reduction of energy consumption in compliance with the objectives set forth in the Army Facilities Energy Plan, without ...
1983-07-01
LOBI/B-R1M, Loop for Blowdown Investigation, PWR Single-Ended Cold-Leg Break Experiment B EXP.B
International Nuclear Information System (INIS)
1 - Description of test facility: The LOBI facility is a 1/700 scale model of a four loop PWR and has two primary loops, the intact loop representing three loops and the broken loop representing one loop of a four-loop PWR. The reactor pressure vessel model contains an electrically heated rod-bundle with 64 rods and a heated length of 3.9 m. The nominal heating power is 5.3 MW. The downcomer is of annular shape. An upper head simulator is connected to the vessel. Each of the two primary loops contains a pump and a steam generator. The different mass flows in the loops are established by the pump speeds, since the two pumps are identical. Heat is removed from the steam generators by a secondary system. ECC water can be supplied from two accumulators, one for each loop. Cold or hot leg as well as combined injection can be simulated. The LOBI test facility is the only high pressure integral test facility ...
United States Domestic Research Reactor Infrastrucutre TRIGA Reactor Fuel Support
Energy Technology Data Exchange (ETDEWEB)
The United State Domestic Research Reactor Infrastructure Program at the Idaho National Laboratory manages and provides project management, technical, quality engineering, quality inspection and nuclear material support for the United States Department of Energy sponsored University Reactor Fuels Program. This program provides fresh, unirradiated nuclear fuel to Domestic University Research Reactor Facilities and is responsible for the return of the DOE-owned, irradiated nuclear fuel over the life of the program. This presentation will introduce the program management team, the universities supported by the program, the status of the program and focus on the return process of irradiated nuclear fuel for long term storage at DOE managed receipt facilities. It will include lessons learned from research ...
2011-03-01
Nuclear Reactor Sharing Program
Energy Technology Data Exchange (ETDEWEB)
The Ohio State University Research Reactor (OSURR) is licensed to operate at a maximum power level of 500 kW. A pool-type reactor using flat-plate, low enriched fuel elements, the OSURR provides several experimental facilities including two 6-inch i.d. beam ports, a graphite thermal column, several graphite-isotope-irradiation elements, a pneumatic transfer system (Rabbit), various dry tubes, and a Central Irradiation Facility (CIF). The core arrangement and accessibility facilitates research programs involving material activation or core parameter studies. The OSURR control room is large enough to accommodate laboratory groups which can use control instrumentation for monitoring of experiments. The control instrumentation is relatively simple, without a large amount of duplication. This facilitates opportunities for hands-on experience in reactor operation by nuclear engineering students making reactor ...
1994-09-01
UK PubMed Central (United Kingdom)
This paper evaluates the Post-Hospital Support Program for the frail elderly and their caregivers using a quasi-experimental design. The program goals were to reduce stress in the caregivers, improve...Full Text Available
1990-01-01
Energy Technology Data Exchange (ETDEWEB)
The two-phase flow program is directed at understanding the hydrodynamics of two-phase flows. The two-phase flow regime is characterized by a series of flow patterns that are designated as bubble, slug, churn, and annular flow. Churn flow has received very little scientific attention. This lack of attention cannot be justified because calculations predict that the churn flow pattern will exist over a substantial portion of the two-phase flow zone in producing geothermal wells. The University of Houston is experimentally investigating the dynamics of churn flow and is measuring the holdup over the full range of flow space for which churn flow exists. These experiments are being conducted in an air/water vertical two-phase flow loop. Brown University has constructed and is operating a unique two-phase flow research facility specifically designed to address flow problems of relevance to the geothermal industry. An important ...
1983-12-01
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 validation of the methods are ...
2009-05-27
FFTF [Fast Flux Test Facility] cesium trap design, installation, and operating experience
International Nuclear Information System (INIS)
The Fast Flux Test Facility (FFTF) is a 400-MWt, sodium-cooled reactor located on the Hanford Site near Richland, Washington, USA. The FFTF is owned by the U.S. Department of Energy and is operated by the Westinghouse Hanford Company. The FFTF was designed to test fuels and materials for use in liquid metal reactors. Since initial operation in 1982, anticipated breaches of experimental fuel pins have released fission products, including cesium, into the primary sodium. Because of its high volatility, cesium vaporizes into the cover gas space, where it condenses on components and equipment and is transported into the cover gas outlet. Because of the long half-life of "1"3"7Cs, these deposits result in long-term, local radiation levels that make contact maintenance difficult. Thus, a cesium trap was installed in FFTF to reduce the cesium level in the sodium. The trap could also permit a Run Beyond Cladding Breach (RBCB) ...
1988-10-17
Analysis of High-Moderation MOX Core MISTRAL-3 with SRAC and MVP
International Nuclear Information System (INIS)
To obtain reactor physics parameters for high-moderation mixed-oxide (MOX) cores, Nuclear Power Engineering Corporation (NPEC), the French Atomic Commission (CEA), and their industrial partners have conducted a MOX core physics experimental program called MISTRAL with the EOLE critical facility of the Cadarache research center. This program consists of four high-moderation cores and was successfully completed in July 2000. This paper describes the analysis results of MISTRAL-3 that is a homogeneous full MOX cylindrical core (H/HM = 6.2) with an 80-cm height and a 59-cm diameter consisting of 1388 standard pressurized water reactor-type MOX fuel rods of 7.0 wt% plutonium-enrichment in a square pitch of 1.39 cm. NPEC has been analyzing the experimental results by using the SRAC and MVP code systems. SRAC and MVP calculate the nuclear core characteristics correctly for the ...
2001-06-17
This paper examines the availability and adequacy of schools' infrastructural facilities for implementation of the Universal Basic Education program in Nigeria. Adopting the "ex post facto" design, the researchers used existing school data on physical facilities, including a survey of key stakeholders in the education sector. Data analysed revealed inadequacy of physical facilities for effective implementation of the UBE program. It was accordingly recommended that government at the national, state and local levels show better commitment to the implementation of the Universal Basic Education program. (Contains 3 figures and 4 tables.)
2008-02-01
Transuranic material recovery in the Integral Fast Reactor fuel cycle demonstration
Energy Technology Data Exchange (ETDEWEB)
The Integral Fast Reactor is an innovative liquid metal reactor concept that is being developed by Argonne National Laboratory. It takes advantage of the properties of metallic fuel and liquid metal cooling to offer significant improvements in reactor safety, operation, fuel cycle economics, environmental protection, and safeguards. The plans for demonstrating the IFR fuel cycle, including its waste processing options, by processing irradiated fuel from the Experimental Breeder Reactor-II fuel in its associated Fuel Cycle Facility have been developed for the first refining series. This series has been designed to provide the data needed for the further development of the IFR program. An important piece of the data needed is the recovery of TRU material during the reprocessing and waste operations.
1993-01-01
Transuranic material recovery in the Integral Fast Reactor fuel cycle demonstration
Energy Technology Data Exchange (ETDEWEB)
The Integral Fast Reactor is an innovative liquid metal reactor concept that is being developed by Argonne National Laboratory. It takes advantage of the properties of metallic fuel and liquid metal cooling to offer significant improvements in reactor safety, operation, fuel cycle economics, environmental protection, and safeguards. The plans for demonstrating the IFR fuel cycle, including its waste processing options, by processing irradiated fuel from the Experimental Breeder Reactor-II fuel in its associated Fuel Cycle Facility have been developed for the first refining series. This series has been designed to provide the data needed for the further development of the IFR program. An important piece of the data needed is the recovery of TRU material during the reprocessing and waste operations.
1993-03-01
Nuclear medicine and imaging research: Quantitative studies in radiopharmaceutical science
Energy Technology Data Exchange (ETDEWEB)
During the past three years the program has undergone a substantial revitalization. There has been no significant change in the scientific direction of this grant, in which emphasis continues to be placed on developing new or improved methods of obtaining quantitative data from radiotracer imaging studies. However, considerable scientific progress has been made in the three areas of interest: Radiochemistry, Quantitative Methodologies, and Experimental Methods and Feasibility Studies, resulting in a sharper focus of perspective and improved integration of the overall scientific effort. Changes in Faculty and staff, including development of new collaborations, have contributed to this, as has acquisition of additional and new equipment and renovations and expansion of the core facilities. 121 refs., 30 figs., 2 tabs.
1991-06-01
Laser application in the fabrication of gas-tagged capsules. A leak detection system
Energy Technology Data Exchange (ETDEWEB)
Encapsulation of a unique isotopic blend of krypton and xenon gas employs a special application of laser technology. The encapsulated gas is then used as the primary medium for detection and identification of failed nuclear fuel rods. The use of gas tagging as a means of detecting and identifying failed nuclear fuel rods has been successfully demonstrated and used by the Argonne National Laboratory, Experimental Breeder Reactor (EBR-2) Project, and the Westinghouse Hanford Company (WHC), Fast Flux Test Facility (FFTF) Fast Breeder Reactor Program. The Power Reactor and Nuclear Fuel Development Corporation (PNC) of Japan has selected this leak detection system for use in their MONJU Prototype Reactor fuel assemblies. The MONJU reactor is almost identical in design to the highly successful FFTF reactor, which is currently in standby status.
1993-12-01
Wind Characteristics at the Vawt Test Facility.
A limited program of field measurements was undertaken in order to define the wind characteristics of the DOE/Sandia vertical axis wind turbine test facility. Because micrometeorological conditions under which a particular wind turbine is tested may have ...
1978-01-01
Energy Technology Data Exchange (ETDEWEB)
This document defines the services the Waste Sampling and Characterization Facility (WSCF) shall provide the Effluent and Environmental Monitoring Program (EEM) throughout the calendar year for analysis. The purpose of the EEM Program is to monitor liquid and gaseous effluents, and the environment immediately around the facilities which may contain radioactive and hazardous materials. Monitoring data are collected, evaluated, and reported to determine their degree of compliance with applicable federal and state regulations and permits.
1998-10-22
The FFTF reactor is described. Procedures and equipment used to protect personnel from potential hazards of oxygen deficient environments are described.
1979-12-12
Evaluation of Commercial Magnetic Descalers.
With the increased costs of maintaining boilers and chillers entrepreneurs around the country have offered magnetic and similar devices to facilities as viable alternatives to their maintenance program. This report gives a brief history of some of the pre...
1984-01-01
Cost Sensitivity Analysis for Radiology Department Planning
UK PubMed Central (United Kingdom)
Two complementary computer programs have been developed for forecasting the demands and evaluating the costs of proposed radiographic facilities. The models are employed here in analyses of the sensitivity...Full Text Available
1971-01-01
Quality Assurance Program Plan for spent fuel handling and packaging
This plan describes the Quality Assurance Program which will be applied to spent fuel handling and packaging tests conducted at the Area 25 E-MAD facility, Nevada Test Site (NTS).
1979-01-31
NPDGamma: A Measurement of the Parity-Violating Gamma Asymmetry A in n-p Capture
Energy Technology Data Exchange (ETDEWEB)
The NPDGamma Experiment measures the parity-violating correlation A{sub {Gamma}Y} between neutron spin and photon momentum in the reaction {rvec n} + p {yields} d + {gamma}. Knowledge of A{sub {Gamma}Y} and other parity-violating observables in few-body nuclear systems will provide constraints for a parameterized description of {Delta}S = 0 parity-violating phenomena free from complications of nuclear structure. The NPDGamma experiment uses a polarized cold pulsed neutron beam, a liquid parahydrogen target, and a cylindrical array of 48 CsI(Tl) scintillation detectors operated in current mode to search for the asymmetry. NPDGamma recently completed the first phase of the program to measure A{sub {Gamma}Y} at the Los Alamos Neutron Science Center with the preliminary result A{sub {Gamma}Y} = (-1.2 {+-} 2.1(stat.) {+-} 0.1(sys.)) x 10{sup -7}, reproducing the previous upper limit from a measurement at a reactor facility. We discuss the ...
2010-01-01
CFD investigation of balcony spill plumes in atria
Energy Technology Data Exchange (ETDEWEB)
Smoke management in buildings during fire events often uses mechanical ventilation systems to maintain smoke layer elevation above a safe evacuation path. Design of these systems requires accurate correlations for the smoke production rate of the buoyant fire plume. One design issue is the smoke production rate of fire plumes which spill out from a fire compartment, under a balcony and up through an atrium or other large volume. Current engineering correlations for these balcony spill plumes are based on a combination of one-tenth scale test data and theoretical analysis. Questions have arisen over the suitability of these correlations for real-scale designs. A combined program of full-scale experimentation and CFD modeling is being conducted to analyze the accuracy of these correlations. A full-scale experimental facility was constructed with a 5 m by 5 m by 15 m fire compartment connected to a ...
2004-07-01
CFD investigation of balcony spill plumes in atria
International Nuclear Information System (INIS)
Smoke management in buildings during fire events often uses mechanical ventilation systems to maintain smoke layer elevation above a safe evacuation path. Design of these systems requires accurate correlations for the smoke production rate of the buoyant fire plume. One design issue is the smoke production rate of fire plumes which spill out from a fire compartment, under a balcony and up through an atrium or other large volume. Current engineering correlations for these balcony spill plumes are based on a combination of one-tenth scale test data and theoretical analysis. Questions have arisen over the suitability of these correlations for real-scale designs. A combined program of full-scale experimentation and CFD modeling is being conducted to analyze the accuracy of these correlations. A full-scale experimental facility was constructed with a 5 m by 5 m by 15 m fire compartment connected to a ...
2004-05-09
The effects of surface damage on RF cavity operation
Energy Technology Data Exchange (ETDEWEB)
We describe a model of damage in rf cavities and show how this damage can limit cavity operation. We first present a review of mechanisms that may or may not affect the ultimate fields that can be obtained in rf cavities, assuming that mechanical stress explains the triggers of rf breakdown events. We present a method of quantifying the surface damage caused by breakdown events in terms of the spectrum of field enhancement factors, Beta, for asperities on the surface. We then model an equilibrium that can develop between damage and conditioning effects, and show how this equilibrium can determine cavity performance and show experimental evidence for this mechanism. We define three functions that quantify damage, and explain how the parameters that determine this performance can be factored out and measured. We then show how this model can quantitatively explain the dependence of cavity performance on material, frequency, pulse length, gas, power supply and other ...
2006-04-14
Progress on fatigue characterization of ITER primary first wall mock-ups
International Nuclear Information System (INIS)
In 2001, EFDA has assigned to ENEA a contract for the thermomechanical testing of six mock-ups of the ITER primary wall module. These small scale mock-ups, reproducing representative portions of the reference ITER primary wall panels, were fabricated during ITER EDA phase by solid hot isostatic pressing (HIPping) of an AISI 316L stainless steel back structure to a alumina dispersion strengthened (DS)-Cu alloy heat sink armored with beryllium tiles. The experimental program, carried-out at ENEA Brasimone CEF 1-2 thermal hydraulic facility, was focused on the thermal mechanical testing of these mock-ups aiming at verifying which tile geometry and manufacturing procedure assures the required reliability of the beryllium/DS-Cu alloy/SS joints at high incident heat flux (>0.8 MW/m"2) both at steady state and under thermal fatigue tests. The paper presents the progress in the experimental activity of the ...
2003-09-01
Energy Technology Data Exchange (ETDEWEB)
Surveillance and maintenance (S & M) of 75 sites were conductd by the Remedial Action Section for the Environmental Restoration Program for surplus facilities and sites contaminated with radioactive materials and/or hazardous chemicals. S & M activities on these sites were conducted from the end of their operating life until final facility disposal or site stabilization. The objectives of the Waste Area Grouping S & M Program are met by maintaining a program of routine S & M as well as by implementing interim corrective maintenance when deemed necessary as a result of site surveillance. This report briefly presents this program`s activities and includes tables indicating tank levels and dry well data for FY 1991.
1991-12-01
Energy Technology Data Exchange (ETDEWEB)
The purpose of this analysis is to develop a systematic program of projects that will result in energy consumption reductions in compliance with the stated goals of the Army Facilities Energy Plan for the Stratford Army Engine Plant in Stratford, Connecticut. Reduced energy consumption is a stated goal for the Army Facility Energy Plan.
1983-08-01
Assessment of the PIUS physics and thermal-hydraulic experimental data bases
Energy Technology Data Exchange (ETDEWEB)
The PIUS reactor utilizes simplified, inherent, passive, or other innovative means to accomplish safety functions. Accordingly, the PIUS reactor is subject to the requirements of 10CFR52.47(b)(2)(i)(A). This regulation requires that the applicant adequately demonstrate the performance of each safety feature, interdependent effects among the safety features, and a sufficient data base on the safety features of the design to assess the analytical tools used for safety analysis. Los Alamos has assessed the quality and completeness of the existing and planned data bases used by Asea Brown Boveri to validate its safety analysis codes and other relevant data bases. Only a limited data base of separate effect and integral tests exist at present. This data base is not adequate to fulfill the requirements of 10CFR52.47(b)(2)(i)(A). Asea Brown Boveri has stated that it plans to conduct more separate effect and integral test programs. If appropriately designed and conducted, ...
1993-12-31
Waste sampling and characterization facility (WSCF) maintenance implementation plan
Energy Technology Data Exchange (ETDEWEB)
This Maintenance Implementation Plan (MIP) is written to satisfy the requirements of the US Department of Energy (DOE) Order 4330.4B, Maintenance Management Program that specifies the general policy and objectives for the establishment of the DOE controlled maintenance programs. These programs provide for the management and performance of cost effective maintenance and repair of the DOE property, which includes facilities. This document outlines maintenance activities associated with the facilities operated by Waste Management Hanford, Inc. (WMH). The objective of this MIP is to provide baseline information for the control and execution of WMH Facility Maintenance activities relative to the requirements of Order 4330.4B, assessment of the WMH maintenance programs, and actions necessary to maintain compliance with the Order. Section 2.0 ...
1997-08-13
Development of in-vessel reflood instrumentation at ORNL
International Nuclear Information System (INIS)
A program under the sponsorship of the United States Nuclear Regulatory Commission was intiated at the Oak Ridge National Laboratory (ORNL) in late 1977. The program, Advanced Instrumentation for Reflood Studies (AIRS), is charged with developing instrumentation for measurement of in-vessel fluid phenomena in pressurized water reactor reflood facilities. The goal of the ORNL program is to develop techniques and systems for measuring fluid flow in-core, deentrainment in the upper plenum and liquid fallback from the upper plenum into the core. A large portion of the development at ORNL is devoted to the impedance probes for measurement of two-phase flow velocities and void fractions. Film probe development at ORNL is limited to adapting the present techniques to the environment of a reflood facility. As the development progresses on all the measurement techniques, ORNL will fabricate ...
2004-09-06
Waste Sampling and Characterization Facility (WSCF). Maintenance Implementation Plan
Energy Technology Data Exchange (ETDEWEB)
This Maintenance Implementation Plan has been developed for maintenance functions associated with the Waste Sampling and Characterization Facility (WSCF). This plan is developed from the guidelines presented by Department of Energy (DOE) Order 4330.4A, Maintenance Management Program (DOE 1990), Chapter II. 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 4330.4A guidelines. In addition, this maintenance plan identifies the actions necessary to develop a cost-effective and efficient maintenance program at WSCF.
1993-07-01
Energy Technology Data Exchange (ETDEWEB)
This report presents the results of the 2003 Radiological Environmental Monitoring Program conducted in accordance with 10 CFR 72.44 for the Fort St. Vrain Independent Spent Fuel Storage Installation. A description of the facility and the monitoring program is provided. The results of monitoring the predominant radiation exposure pathway, direct radiation exposure, indicate the facility operation has not contributed to any increase in the estimated maximum potential dose commitment to the general public.
2001-02-01
Energy Technology Data Exchange (ETDEWEB)
This report presents the results of the 2001 Radiological Environmental Monitoring Program conducted in accordance with 10 CFR 72.44 for the Fort St. Vrain Independent Spent Fuel Storage Installation. A description of the facility and the monitoring program is provided. The results of monitoring the predominant radiation exposure pathway, direct and scattered radiation exposure, indicate the facility operation has not contributed to any increase in the estimated maximum potential dose commitment to the general public.
2002-02-01
The status of the alpha-project
International Nuclear Information System (INIS)
A review of the ALPHA project is presented, including a summary of progress and current status. The project comprises the experimental and analytical investigation of the long-term decay heat removal phenomena from the containment of the next generation of ''passive'' Advanced Light Water Reactors. The effects of aerosols that may result from hypothetical severe accidents are also considered. The construction of the major ALPHA experimental facilities, PANDA, LINX-2 and AIDA, has been completed. First steady-state tests have been performed on PANDA. The other facilities are now in their commissioning phases. Scaling studies have guided the design of the experimental facilities. Several small-scale experimental and studies have already produced valuable results which can be used to direct the experimental work, as well as ...
1996-04-01
Status of FFTF startup program and future FFTF utilization
International Nuclear Information System (INIS)
A brief FFTF project description is provided which includes general plant siting information, general layout, plant design parameters, description of principal systems and components, and description of support facilities. The current status of the FFTF project is provided, including status of plant construction, overall status of the plant checkout and test program, status of operating authorization and plant operating procedures and personnel, and status of reactor core components and experiments. Specific information on the acceptance test program and early program results is discussed. The role of FFTF in the future breeder program is described, including its objectives for verification of plant system and components designs and operability and use as an irradiation test facility.
1978-10-25
Abstracts of recent reports: Maryland power plant research program 1992 through 1997
Energy Technology Data Exchange (ETDEWEB)
The goals of the program include predicting the impact of proposed new generating facilities, evaluating proposed high voltage transmission lines, assessing the impact of existing generating facilities, forecasting future demand for electric power, and investigating numerous information gaps through a long-range research program. The Power Plant Assessment Division (PPAD) is responsible for all PSC licensing support, site specific research, and radiological monitoring. The list of reports summarizes information of over 190 technical publications that represent the Program`s formalized research and monitoring efforts over the last five years. Reports are listed in chronological order by topical heading.
1997-12-01
Session 1: Geothermal Pumping Systems and Two-Phase Flow Studies
Energy Technology Data Exchange (ETDEWEB)
Improvements in electric submersible pumping systems have resulted in a demonstrated downhole running life of one year for low horsepower units operating in 180 C brine. The implementation of a prototype pressurized lubrication system to prevent brine intrusion and loss of lubricating oil from the motor and protector sections has been successfully tested. Second generation pressurized lubrication systems have been designed and fabricated and will be utilized in downhole production pumping tests during FY84. Pumping system lifetime is currently limited by available power cable designs that are degraded by high-temperature brine. A prototype metal-sheathed power cable has been designed and fabricated and is currently undergoing destructive and nondestructive laboratory testing. This cable design has the potential for eliminating brine intrusion into the power delivery system through the use of a hermatically sealed cable from the surface to the downhole motor. The two-phase flow ...
1983-12-01
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 ...
International Nuclear Information System (INIS)
CORAL-I was an experimental, zero-power, fast-spectrum, high-enriched metal uranium reactor that operated from 1968 until 1988 at the former Junta de Energia Nuclear (JEN), CIEMAT at present. The critical measurements performed at the startup of the reactor are being evaluated as part of the International Critical Safety Benchmark Evaluation Program (ICSBEP) and proposed to be included in its 2001 edition. Additionally, the measurement of the mass reactivity coefficient is compared with MCNP4B calculations. This measurement allows one to perform the approach to critical without the need of a previous control rod calibration, thus enhancing the safety of such an approach. This technique can also be applied to other reactor types. CORAL-I (Ref. 1) is a 90% enriched metal uranium reactor domestically designed and manufactured in the experimental facilities of JEN, now CIEMAT, in Madrid, Spain. The enriched ...
2001-06-17
Dynamics and developing of natural circulation cooling from vertical upflow and downflow conditions
International Nuclear Information System (INIS)
Several research programs have been conducted to evaluate the capability of natural circulation cooling of reactors following a loss of cooling accident. Both experimental and RELAP5 simulation results were obtained for these studies in a facility with vertical heated tube(s) and a unheated bypass channel. The analytical results showed that, under a certain power level, a natural circulation pattern can be developed from both initial upflow and downflow conditions, and maintained for a significant cooling period. This power level, for the discussion of this paper, is defined as the natural circulation cooling (NCC) power limit. Two import factors, namely the pump coastdown rate and the initial flow direction, are examined in this paper. In the benchmark case, as compared to the experimental results, the RELAP5 simulation program accurately predicted the transient phenomena from ...
1994-04-05
Summary on experimental facilities and future developments at SINQ
Energy Technology Data Exchange (ETDEWEB)
With 13 experimental facilities under construction to become available during the first year of SINQ operation, a nearly complete suite of options for users will be made available to carry out research with neutrons at PSI. Three more facilities are under design and will come on line somewhat later. To complete the suite, three more specialized instruments are being evaluated. SINQ being a novel neutron source concept, significant scope for improvement is also seen on the source side. It is a major goal of PSI to exploit these opportunities and to make - among others - use of neutron instruments to carry out the necessary research. (author) 9 figs., 1 tab., 11 refs.
1996-11-01
Natural circulation in FFTF, a loop type LMFBR
International Nuclear Information System (INIS)
The authors present a state-of-the-art review of natural circulation heat transfer in loop type reactor plants. Most of the examples are taken from Fast Flux Test Facility (FFTF) design experience, drawing on the authors' familiarity and a developing base of available documentation. On-going studies related to the Clinch River Breeder Reactor (CRBR) and some foreign experience are also noted where available in the literature. The emphasis is on the role of natural circulation in decay heat removal; however, free convection during either operation at power or normal shutdown does influence some aspects of the design and these are reviewed. In treating decay heat removal the topics discussed include steady state loop performance and transient dynamics for conditions immediately after scram and for the longer term which involves different considerations. The review summarizes complex dynamics, specific to the FFTF design evaluation, which particularly illustrate large ...
Development of radioisotope tracer technology
Energy Technology Data Exchange (ETDEWEB)
The purpose of this study is to develop the radioisotope tracer technology, which can be used in solving industrial and environmental problems and to build a strong tracer group to support the local industries. In relation to the tracer technology in 1999, experiments to estimate the efficiencies of a sludge digester of a waste water treatment plant and a submerged biological reactor of a dye industry were conducted. As a result, the tracer technology for optimization of facilities related to wastewater treatment has been developed and is believed to contribute to improve their operation efficiency. The quantification of the experimental result was attempted to improve the confidence of tracer technology by ECRIN program which basically uses the MCNP simulation principle. Using thin layer activation technique, wear of tappet shim was estimated. Thin layer surface of a tappet shim was irradiated by proton beam and the ...
2000-04-01
UK PubMed Central (United Kingdom)
Since the establishment of the National Toxicology Program (NTP), there have been gradual changes in strategies to evaluate the overall toxicity of chemicals as well as their carcinogenic potential....Full Text Available
1990-06-01
Environmental Restoration Program quality assurance system requirements for the Hanford Site
International Nuclear Information System (INIS)
This document defines the quality assurance program requirements for the US Department of Energy, Richland Field Office, Environmental Restoration program at the Hanford Site. This document integrates quality assurance requirements from US Department of Energy Orders, the Hanford Federal Facility Agreement and Consent Order, and applicable industry standards into a single source document for the development of quality assurance programs applicable to the Environmental Restoration program items and activities. This document has been configured into three parts and fifteen criteria to provide user organizations with a workable document that best facilitates line operations. When developing individual user organization quality assurance programs, the document configuration provides each organization with the Flexibility to incorporate only those parts and criteria ...
UK PubMed Central (United Kingdom)
OBJECTIVE: To evaluate the effectiveness of a program to improve hypertension control practices in primary care. DESIGN: Retrospective quasi-experimental study. SETTING: Three hospital-based family...Full Text Available
1994-10-01
Surveillance and maintenance activities of waste area groupings at Oak Ridge National Laboratory
Energy Technology Data Exchange (ETDEWEB)
Surveillance and maintenance (S M) of 75 sites were conductd by the Remedial Action Section for the Environmental Restoration Program for surplus facilities and sites contaminated with radioactive materials and/or hazardous chemicals. S M activities on these sites were conducted from the end of their operating life until final facility disposal or site stabilization. The objectives of the Waste Area Grouping S M Program are met by maintaining a program of routine S M as well as by implementing interim corrective maintenance when deemed necessary as a result of site surveillance. This report briefly presents this program's activities and includes tables indicating tank levels and dry well data for FY 1991.
1991-12-01
Experimental study of axial and crossflow velocity in a 7-pin wire wrapped bundle
The results of an experimental study of axial and crossflow velocity in a 7-pin wire wrapped bundle similar for FFTF fuel bundles are reported. The results are compared with the forced crossflow model of the COBRA-III C computer program. (JWR)
1974-02-01
Implementation plan: Quality assurance requirements: Hazardous Waste Remedial Actions Program
International Nuclear Information System (INIS)
This document establishes the Quality Assurance (QA) Program requirements for the Hazards Waste remedial Actions Program (HASWRAP) for ensuring, with a high degree of confidence, that program objectives will be achieved as planned. The QA Program is introduced in Sect. 1. The HAZWRAP Support Contractor Office (SCO) functional organization and QA responsibilities are shown in Sect. 2. QA program requirements are contained in Sect. 3. These requiremens are pased on the American national Standard, American National Standards Institute/American Society of Mechanical Engineers NQA-1 Quality Assurance Program Requirements for Nuclear Facilities. The 18 elements defined in the standard are tailored to HAZWRAP's needs. The QA program requirements are delineated under the major headings: Quality Assurance ...
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, ...
1986-12-01
Argonne National Laboratory-East evolution of solid waste management
Energy Technology Data Exchange (ETDEWEB)
The purpose of this report is to provide the reader with a basic understanding of Argonne National Laboratory`s current general refuse disposal and material recycling programs, how they were developed, and where they are going. In order to better understand the current situation, a brief description of the facilities past practices is explained. ANL is a multi-program research and development center owned by DOE and operated by the University of Chicago. Argonne`s primary facilities are on a 1,700 acre site, 27 miles southwest of Chicago. Fifty-seven major buildings house approximately 4,500 employees at the site.
1996-07-01
A decade of waste and pollution management
Energy Technology Data Exchange (ETDEWEB)
The purpose of this report is to provide the reader with a basic understanding of Argonne National Laboratory`s current general refuse disposal and material recycling programs, how they were developed, and where they are going. In order to better understand the current situation, a brief description of the facilities past practices is explained. ANL is a multi-program research and development center owned by the U.S. Department of Energy (DOE) and operated by the University of Chicago. Argonne`s primary facilities are on a 1,700 acre site, 27 miles southwest of Chicago. Fifty-seven major buildings house approximately 4,500 employees at the site.
1996-10-01
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 ...
1996-01-01
Energy Technology Data Exchange (ETDEWEB)
The International Atomic Energy Agency (IAEA) started the Coordinated Research Program entitled ```The Safety Assessment of Near-Surface Radioactive Waste Disposal Facilities.`` The program is aimed at improving the confidence in the modeling results for safety assessments of waste disposal facilities. The program has been given the acronym NSARS (Near-Surface Radioactive Waste Disposal Safety Assessment Reliability Study) for ease of reference. The purpose of this report is to present the ORNL modeling results for the first test case (i.e., Test Case 1) of the IAEA NSARS program. Test Case 1 is based on near-surface disposal of radionuclides that are subsequently leached to a saturated-sand aquifer. Exposure to radionuclides results from use of a well screened in the aquifer and from intrusion into the repository. Two repository concepts were defined in Test ...
1993-07-01
Energy Technology Data Exchange (ETDEWEB)
The EMP consists of a Compliance Monitoring Sampling Program and a Supplemental monitoring Sampling Program. The Compliance Monitoring Sampling Program will be conducted during a summer and a winter Baseline periods during the Pre-Construction/Construction phases of the Project and during a summer and a winter period following the successful Startup and Operational phase of the completed Project. compliance monitoring consist of conducting all the sampling and observation programs associated with existing required Federal, State, and Local Regulations, Permits and Orders. These include air, water, and waste monitoring and OSHA and NESHAP monitoring. The Supplemental Monitoring Program will also be conducted during a summer and a winter Baseline periods during the Pre-Construction/Construction phases of the Demonstration Facility and during a summer and a winter ...
1992-09-21
Innovative coke oven gas cleaning system for retrofit applications
Energy Technology Data Exchange (ETDEWEB)
The EMP consists of a Compliance Monitoring Sampling Program and a Supplemental monitoring Sampling Program. The Compliance Monitoring Sampling Program will be conducted during a summer and a winter Baseline periods during the Pre-Construction/Construction phases of the Project and during a summer and a winter period following the successful Startup and Operational phase of the completed Project. compliance monitoring consist of conducting all the sampling and observation programs associated with existing required Federal, State, and Local Regulations, Permits and Orders. These include air, water, and waste monitoring and OSHA and NESHAP monitoring. The Supplemental Monitoring Program will also be conducted during a summer and a winter Baseline periods during the Pre-Construction/Construction phases of the Demonstration Facility and during a summer and a winter ...
1992-09-21
Energy Technology Data Exchange (ETDEWEB)
Since 1976, the Nuclear Engineering Laboratory of the Technical Research Centre of Finland and Lappeenranta University of Technology have cooperated in the field of nuclear reactor thermal-hydraulics. During these years, a series of experimental facilities (REWET-I, -II, -III, VEERA) simulating pressurized water reactors (PWRs) have been built. The newest facility, PACTEL (Parallel Channel Test Loop), is an experimental out-of-pile facility designed to simulate the major components and system behaviour of a commercial PWR during postulated small and medium size break loss-of-coolant accidents (LOCAs), natural circulation and operational transients. A PACTEL natural circulation experiment has been carried out as an OECD/NEA international standard problem ISP 33. (2 refs., 3 figs., 2 tabs.).
1993-12-31
Quality assurance requirements for the design of nuclear fuel reprocessing facilities
International Nuclear Information System (INIS)
Requirements and guidance are provided for a quality assurance program for the design of nuclear fuel reprocessing facilities involving structures, systems and components whose satisfactory performance is required to prevent accidents that could cause undue risk to the health and safety of the public, or to mitigate the consequences of such accidents if they were to occur. The standard is to be used in conjunction with ANSI N46.2.
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
Risk evaluation system for facility safeguards and security planning
International Nuclear Information System (INIS)
The Risk Evaluation System (RES) is an integrated approach to determining safeguards and security effectiveness and risk. RES combines the planning and technical analysis into a format that promotes an orderly development of protection strategies, planning assumptions, facility targets, vulnerability and risk determination, enhancement planning, and implementation. In addition, the RES computer database program enhances the capability of the analyst to perform a risk evaluation of the facility. The computer database is menu driven using data input screens and contains an algorithm for determining the probability of adversary defeat and risk. Also, base case and adjusted risk data records can be maintained and accessed easily.
1987-07-12
Maintenance implementation plan for T Plant. Revision 2
Energy Technology Data Exchange (ETDEWEB)
This document is a Maintenance Implementation Plan (MIP) for the T Plant Facility complex located in the 200 West Area of the Hanford Reservation in Washington state. This plan has been developed to provide a disciplined approach to maintenance functions and to describe how the T Plant facility will implement and comply with the regulations according to US DOE order 4330.4B, entitled Maintenance Management Program, Chapter 2.0 {open_quotes}Nuclear Facilities{close_quotes}. Physical structures, systems, processes, as well as all associated equipment specifically assigned to these groups are included in the MIP.
1995-05-01
Facility Safety Plan B360 Complex Biohazardous Operations CMLS-412r0
This Addendum to the Facility Safety Plan (FSP) 360 Complex describes the safety requirements for the safe conduct of all biohazardous research operations in all buildings within the 360 complex program areas. These requirements include all the responsibilities and authorities of building personnel, operational hazards, and environmental concerns and their controls. In addition, this Addendum prescribes facility-specific training requirements and emergency controls, as well as maintenance and quality assurance requirements for ES&H-related building systems.
2007-01-08
The PANDA tests for SBWR certification
International Nuclear Information System (INIS)
The ALPHA project is centered around the experimental and analytical investigation of the long-term decay heat removal from the containments of the next generation of open-quotes passiveclose quotes ALWRs. The project includes integral system tests in the large-scale (1:25 in volume) PANDA facility as well as several other series of tests and supporting analytical work. The first series of experiments to be conducted in PANDA have become a required experimental element in the certification process for the General Electric Simplified Boiling Water Reactor (SBWR). The PANDA general experimental philosophy, facility design, scaling, and instrumentation are described. Steady-state PCCS condenser performance tests and extensive facility characterization tests were already conducted. The transient system behavior tests are underway; preliminary results from the first ...
1996-03-01
SEER Program Code Manual 3rd Edition, Revision 1 - SEER Field and Code Changes for 2003
Changes to SEER Data Set for 2003 SEER Program Code Manual, 3rd Edition, 1st revision Data Items Required by SEER but No Longer Collected by COC The following fields will still be required by SEER or its participating central registries, even though they will no longer be collected by Commission on Cancer-approved facilities.
Quality assurance on the Idaho National Engineering Laboratory Buried Waste Program
International Nuclear Information System (INIS)
This paper discusses the clean-up of an Idaho National Engineering Laboratory (INEL) site utilized for disposal of transuranic contaminated waste from 1954 until 1970. The author presents requirements of the environmental protection statutes that have generated quality assurance requirements in addition to those historically implemented as a part of facility design, construction and operation. A hierarchy of program guidance quality documentation and procedures is discussed. Data qualification and computer database management are identified as requirements.
1989-04-02
Irradiation test program for FFTF
International Nuclear Information System (INIS)
Four unique deisgn features are described which make the Fast Flux Test Facility eminently suitable for irradiation test programs. These features are a fast flux level of 7 x 10"1"5 neutrons/cm"2/sec, a 36-inch reference (breeder reactor) core height, test volumes suitable for testing of statistical quantities of materials, and the capability for direct (contact) or indirect (proximity) instrumentation of active core experiments.
INL Advanced Radiotherapy Research Program Annual Report 2004
Energy Technology Data Exchange (ETDEWEB)
This report summarizes the activities and major accomplishments for the Idaho National Laboratory Advanced Radiotherapy Research Program for calendar year 2004. Topics covered include boron analysis in biological samples, computational dosimetry and treatment planning software development, medical neutron source development and characterization, and collaborative dosimetry studies at the RA-1 facility in Buenos Aires, Argentina.
2005-06-01
Energy analysis for Fort McNair, Marshall Hall
Marshall Hall was selected by the US Army Corps of Engineers to participate in the Energy Efficiency Analysis Program. The objective of this program is to assist military installations in identifying energy usage and cost saving projects at their facilities and possibly provide funding for projects. Entech Engineering, Inc. was selected to perform this study.
1995-08-01
Energy Technology Data Exchange (ETDEWEB)
The report presents a brief synopsis and discussion of wildlife activities undertaken by Bonneville Power Administration. The objectives of the program were wildlife protection, mitigation, and enhancement planning; and implementation of actions to protect, mitigate, and enhance wildlife affected by development and operation of hydroelectric facilities in the Columbia River Basin. (ACR)
1985-09-01
ENGINEERING DEVELOPMENT OF COAL-FIRED HIGH-PERFORMANCE POWER SYSTEMS
Energy Technology Data Exchange (ETDEWEB)
A High Performance Power System (HIPPS) is being developed. This system is a coal-fired, combined cycle plant with indirect heating of gas turbine air. Foster Wheeler Development Corporation and a team consisting of Foster Wheeler Energy Corporation, Bechtel Corporation, University of Tennessee Space Institute and Westinghouse Electric Corporation are developing this system. In Phase 1 of the project, a conceptual design of a commercial plant was developed. Technical and economic analyses indicated that the plant would meet the goals of the project which include a 47 percent efficiency (HHV) and a 10 percent lower cost of electricity than an equivalent size PC plant. The concept uses a pyrolyzation process to convert coal into fuel gas and char. The char is fired in a High Temperature Advanced Furnace (HITAF). The HITAF is a pulverized fuel-fired boiler/air heater where steam is generated and gas turbine air is indirectly heated. The fuel gas generated in the pyrolyzer is then used to ...
1998-10-01
Managing system for mounted parts and spare parts of power source facilities
Energy Technology Data Exchange (ETDEWEB)
The power source facilities of JT-60 consist of poloidal magnetic coil power source, toroidal magnetic coil power source, the power generation facility for heating, operation power distribution facility and secondary cooling facility, and at the time of the experiment operation of JT-60, they supply 1300 MVA of instantaneous maximum power to loads. The component machinery and equipment of the power source facilities are installed in about 20 indoor and outdoor places, and their mounted parts are about 15,000 kinds. About 3,000 kinds of spare parts are preserved in 15 exclusively used stores. The managing system for mounted parts and spare parts of JT-60 power source facilities which possesses the functions of rapidly and efficiently carrying out the storage of large quantity of information, mutual relating and retrieval by making mounted parts and spare parts ...
1995-07-01
Energy Technology Data Exchange (ETDEWEB)
Because of past military operations, lack of upkeep and looting there are now enormous radioactive waste problems in Iraq. These waste problems include destroyed nuclear facilities, uncharacterized radioactive wastes, liquid radioactive waste in underground tanks, wastes related to the production of yellow cake, sealed radioactive sources, activated metals and contaminated metals that must be constantly guarded. Iraq currently lacks the trained personnel, regulatory and physical infrastructure to safely and securely manage these facilities and wastes. In 2005 the International Atomic Energy Agency (IAEA) agreed to organize an international cooperative program to assist Iraq with these issues. Soon after, the Iraq Nuclear Facility Dismantlement and Disposal Program (the NDs Program) was initiated by the U.S. Department of State (DOS) to support the IAEA and ...
2009-03-01
The Los Alamos National Laboratory Environmental Restoration Program
Energy Technology Data Exchange (ETDEWEB)
The LANL Environmental Restoration (ER) Program Office, established in October 1989, is faced with the challenge of assessing and cleaning up nearly 1,8000 potentially hazardous waste sites according to an aggressive corrective action schedule that the Environmental Protection Agency (EPA) mandated on May 23, 1990, in a Resource, Conservation, and Recovery Act (RCRA) Part B Permit. To maximize program efficiency, the ER Program Office will implement a unique management approach designed to maximize the use of laboratory technical expertise. The Installation Work Plan, which provides a blueprint for the program, has been submitted to EPA for review and approval. A work plan for characterization of Technical Area 21, an early plutonium processing facility, is also nearing completion. The feasibility of an expedited cleanup of the Laboratory's worst hazardous waste release has ...
1990-01-01
Energy Technology Data Exchange (ETDEWEB)
The Next Generation Nuclear Plant (NGNP), a demonstration reactor and hydrogen production facility proposed for construction at the INEEL, is expected to be a high-temperature gas-cooled reactor (HTGR). Computer codes used in design and safety analysis for the NGNP must be benchmarked against experimental data. The INEEL and ANL have examined information about several past and present experimental and prototypical facilities based on HTGR concepts to assess the potential of these facilities for use in this benchmarking effort. Both reactors and critical facilities applicable to pebble-bed and prismatic block-type cores have been considered. Four facilities--HTR-PROTEUS, HTR-10, ASTRA, and AVR--appear to have the greatest potential for use in benchmarking codes for pebble-bed reactors. Similarly, for the prismatic block-type reactor design, ...
2005-10-25
Adapting United States training practices to European utilities
International Nuclear Information System (INIS)
The factors which must be considered in the process of adapting United States nuclear utility training programs to the needs of a European utility are discussed. Following a review of the present situation and drawing up of a new training program, the management commitments in terms of personnel and finance must be considered. Short term, medium and long term programs are outlined. The long term objectives should include the establishment of a total training centre. This facility should be capable of providing all the training necessary to operate a power plant safely. This would include specific simulator training, classroom training for operators, technician training, staff training, management training etc. In addition to a simulator, it should include an emergency response facility to train personnel. (U.K.).
Environmental restoration remedial action quality assurance requirements document
International Nuclear Information System (INIS)
The environmental Restoration Remedial Action Quality Assurance Requirements Document (DOE/RL 90-28) defines the quality assurance program requirements for the US Department of Energy-Richland Field Office Environmental Restoration Remedial Action Program at the Hanford Site, Richland, Washington. This paper describes the objectives outlined in DOE/RL 90-28. The Environmental Restoration Remedial Action Program implements significant commitments made by the US Department of Energy in the Hanford Federal Facility Agreement and Consent Order entered into with the Washington State Department of Ecology and the US Environmental Protection Agency.
1991-09-08
Development of the SRS environmental counting laboratory gamma spectroscopy system
International Nuclear Information System (INIS)
The Savannah River Site (SRS), one of several U.S. Department of Energy (DOE) facilities, produces nuclear materials for national defense and for other government and civilian uses. SRS ceased production of defense materials in 1988, and the site's main activities now involve waste management and environmental restoration. These programs have generated extensive effluent monitoring and environmental surveillance programs for the Environmental Monitoring Section (EMS), which performs #approx#105,000 radiological analyses on 30,000 samples a year. Gamma spectroscopy is performed on an estimated 10,000 samples annually. This report describes a program to develop and improve the EMS system.
1996-06-16
Energy Technology Data Exchange (ETDEWEB)
A description of the FEL experiment underway at the 10 kA, 5 MeV Experimental Test Accelerator (ETA) is described. The facility has been designed to investigate the high-gain operation of an FEL.
1983-09-19
Guided Cell Migration on Microtextured Substrates with Variable Local Density and Anisotropy
UK PubMed Central (United Kingdom)
This work reports the design of and experimentation with a topographically patterned cell culture substrate of variable local density and anisotropy as a facile and efficient platform to guide...Full Text Available
2009-02-06
Computing needs of the superconducting super collider
Energy Technology Data Exchange (ETDEWEB)
Following a brief description of the SSC, the computing needs are discussed for both the accelerator design and the experimentation. The computing power required is considerably beyond that being used at present facilities, and parallel processing is expected to play an important role in supplying these needs.
1984-01-01
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 ...
1999-02-01
International Nuclear Information System (INIS)
Based on the occurrence of a number of plant incidents during low power and shutdown operating conditions, the Nuclear Regulatory Commission (NRC) has initiated several programs to better quantify risk during these periods. One specific issue of interest is the loss of residual heat removal (RHR) under reduced coolant inventory conditions. This issue is also of interest in the Federal Republic of Germany and an experiment was performed in the integral PKL-3 experimental facility at Siemens-KWU to supply applicable data. Recently, an effort has been undertaken at the Idaho National Engineering Laboratory (INEL) to identify and analyze the important thermal-hydraulic phenomena in pressurized water reactors following loss of vital AC power and consequent loss of the RHR system during reduced inventory operation. The thermal-hydraulic response of a nuclear steam supply system (NSSS) with a closed reactor coolant system (RCS) to ...
1991-10-01
International Nuclear Information System (INIS)
This study evaluates the degree to which surface impoundments at licensed facilities comply with significant changes in NRC requirements initiated by enactment of EPA's final environmental standards for uranium recovery facilities (40 CFR Part 192). Impoundment liner requirements, ground-water protection standards, ground-water monitoring and corrective action programs, and site closure standards are the most significant regulatory modifications. The compliance status of 30 conventional mills and 31 in-situ mines is determined from a review of Nuclear Regulatory Commission and agreement state docket files through November, 1983. Results of this review show that a majority of conventional uranium mill tailings management systems are deficient with respect to liner requirements for new impoundments or proposed expansions to existing impoundments, as well as with respect to some aspects of ground-water monitoring and ...
Hot Cell Facility (HCF) Safety Analysis Report
Energy Technology Data Exchange (ETDEWEB)
This Safety Analysis Report (SAR) is prepared in compliance with the requirements of DOE Order 5480.23, Nuclear Safety Analysis Reports, and has been written to the format and content guide of DOE-STD-3009-94 Preparation Guide for U. S. Department of Energy Nonreactor Nuclear Safety Analysis Reports. The Hot Cell Facility is a Hazard Category 2 nonreactor nuclear facility, and is operated by Sandia National Laboratories for the Department of Energy. This SAR provides a description of the HCF and its operations, an assessment of the hazards and potential accidents which may occur in the facility. The potential consequences and likelihood of these accidents are analyzed and described. Using the process and criteria described in DOE-STD-3009-94, safety-related structures, systems and components are identified, and the important safety functions of each SSC are described. Additionally, information which describes the safety ...
2000-11-01
Radionuclide buildup in FFTF [Fast Flux Test Facility] heat transport system cells
International Nuclear Information System (INIS)
The purpose of the work reported in this paper was to measure the radionuclide buildup in primary heat transport system cell No. 3 at the Fast Flux Test Facility (FFTF) and to compare the results with predicted values from a model based on experimental studies and experience at similar reactors. The information obtained is used for maintenance planning and to enhance ability to assess radionuclide buildup in the future at FFTF and in other reactors.
1989-11-26
Evaluation of the SYNTHOIL process. Volume II. Status of development. [47 refs
The Synthoil process for producing heavy desulfurized fuel oil from coal has been under development at Pittsburgh Energy Research Center since 1969. The status of development and technical feasibility of the process are reviewed. This is part of an engineering and economic evaluation based on the conceptual design of a 100,000-bbl/day commercial Synthoil facility. Experimental data are discussed with regard to their adequacy for the formulation of a basis for the process design of such a facility. Potential engineering and equipment problems are analyzed.
1977-06-01
An analysis of convective losses from cavity solar central receivers
Energy Technology Data Exchange (ETDEWEB)
A simple analytical model has been developed in order to provide a framework for designing experimental programs for convective loss determinations, for analyzing available experimental data from solar receiver test programs, and for estimating the convective loss at a relatively small cost. Analytical results and experimental evidence indicate that the convective loss from cavity receivers is appreciable, while the effects of wind on the convective loss under normal operating conditions are minimal. The proposed analytical model provides a means of determining the relative importance of the internal resistances and predicting the bulk air temperature within the convective zone inside the cavity.
1981-01-01
Hyperfine structure studies with the COMPLIS facility
International Nuclear Information System (INIS)
COMPLIS is an experimental facility designed to carry out spectroscopic studies on radioisotopes produced by disintegration of elements available at CERN's Booster-ISOLDE on-line isotope separator. During recent series of experimental runs, hyperfine structure measurements have yielded information on nuclear moments and deformations of platinum and iridium isotopes. For the first time, population by #alpha#-decay from Hg was exploited to investigate "1"7"8"-"1"8"1Pt--the most neutron-deficient Pt isotopes yet studied. Successful measurements have recently been carried out on "1"8"2"-"1"8"9Ir.
1998-12-16
Environmental Restoration Remedial Action quality assurance requirements document
International Nuclear Information System (INIS)
This document defines the quality assurance requirements for the US Department of Energy-Richland Operations Office Environmental Restoration Remedial Action program at the Hanford Site. The Environmental Restoration Remedial Action program implements significant commitments made by the US Department of Energy in the Hanford Federal Facility Agreement and Consent Order entered into with the Washington State Department of Ecology and the US Environmental Protection Agency. This document combines quality assurance requirements from various source documents into one set of requirements for use by the US Department of Energy-Richland Operations Office and other Environmental Restoration Remedial Action program participants. This document will serve as the basis for developing Quality Assurance Program Plans and implementing procedures by the participants. The requirements of this ...
Groundwater surveillance plan for the Oak Ridge Reservation
Energy Technology Data Exchange (ETDEWEB)
US Department of Energy (DOE) Order 5400.1 requires the preparation of environmental monitoring plans and implementation of environmental monitoring programs for all DOE facilities. The order identifies two distinct components of environmental monitoring, namely effluent monitoring and environmental surveillance. In general, effluent monitoring has the objectives of characterizing contaminants and demonstrating compliance with applicable standards and permit requirements, whereas environmental surveillance has the broader objective of monitoring the effects of DOE activities on on- and off-site environmental and natural resources. The purpose of this document is to support the Environmental Monitoring Plan for the Oak Ridge Reservation (ORR) by describing the groundwater component of the environmental surveillance program for the DOE facilities on the ORR. The distinctions between groundwater effluent ...
1994-07-01
International Nuclear Information System (INIS)
Neutron energy spectra were measured for two OSURR experimental facilities. The method of multiple foil activation was used with the SAND-II neutron spectrum unfolding code to obtain spectral data for the Central Irradiation Facility and Rabbit tube. Limited data was obtained for the thermal column using only gold foils. Calculations were made of the neutron environment in various locations using the MORSE code. A shift towards higher neutron energies was observed comparing results for LEU and HEU cores. A slight loss in total thermal neutron flux was measured for all positions. Calculational results show reasonable agreement with measured data.
1993-07-01
The paper briefly describes the nuclear reactor facilities at Sandia Laboratories which are used for simulating nuclear weapon produced neutron environments. These reactor facilities are used principally in support of continuing R and D programs for the Department of Energy/Office of Military Application (DOE/OMA) in studying the effects of radiation on nuclear weapon systems and components. As such, the reactors are available to DOE and DOD agencies and their contractors responsible for the radiation hardening of advanced nuclear weapon systems. Emphasis is placed upon two new reactor simulation sources; the Sandia Pulse Reactor-III (SPR-III) Facility which enhances the neutron exposure volume capabilities over those presently available with the existing SPR-II Facility, and the Upgraded Annular Core Pulse Reactor (ACPR) Facility which enhances the neutron ...
1978-07-01
International Nuclear Information System (INIS)
Due to current social and economical framework, in last years many nuclear power plant owners started a program for the Long Term Operation (LTO)/PLIM (Plant Life Management) of their older nuclear facilities. PLIM/PLEX has already been implemented in many countries (USA, Russia, etc.). This process has many nuclear safety implications, other than strategic and political ones. The need for tailoring the available safety assessment tools to such applications has become urgent in recent years and triggered many research actions. In particular, a PLIM framework requires both a detailed review of the features of the main safety programs (Maintenance, ISI, Surveillance) and a complete integration of these programs into the general management system of the plant. New external factors, such as: large use of subcontractors, need for efficient management of spare parts, request for heavy plant refurbishment ...
2007-10-15
International Nuclear Information System (INIS)
The nuclear complex in Tarapur, Maharashtra is a multi facility nuclear site comprising of power reactors and research facilities. Each facility has independent liquid effluent discharge line to Arabian Sea. Experimental studies were conducted to evaluate dilution factors in the aquatic environment using liquid effluent releases as tracer from one of the facilities. 3H and 137Cs radioisotopes present in the routine releases were used as simulated tracer nuclides. The dilution factors(D.F) observed for tritium were in the range of 20-20000 in a distance range of 10 m to 1500 m respectively and for 137Cs the D.F. were in the range of 50 to 900 over a distance range of 10-200 m. The paper describes the analytical methodology and sampling scenarios and the results of dilution factors obtained for Tarapur aquatic environment. (author)
2007-06-05
Research and development of neutron radiography in IAERU
Energy Technology Data Exchange (ETDEWEB)
In the Institute for Atomic Energy, Rikkyo University, just after the TRIGA-2 research reactor of 100 kW has attained the criticality, the cylindrical box for neutron radiography (NR) irradiation was made in the attached pool, and the research on NR was started in 1961. Thereafter in 1985, the vertical irradiation pipe was installed in the reactor tank, and the experiment for collecting the basic data was begun. In 1986, based on the obtained data, the NR irradiation facility on full scale was installed in No. 2 tangential horizontal experimental hole. As the main NR irradiation facilities, the vertical neutron irradiation pipe, the use of which is stopped now, the NR facility using the horizontal experimental hole (RUR/N2), the irradiation facility and ancillary facilities such as beam shutter, beam catcher and hoist are described. As the ...
1995-03-01
Utility applications program. Annual report for 1981
Energy Technology Data Exchange (ETDEWEB)
The purpose of the Utility Applications Program is to provide information and assistance to interested utilities on central station energy storage systems. Compressed air and underground pumped hydroelectric energy storage are the primary technical focus. Smaller utilities are the primary targets of this program, as they may not have resources to track and utilize new energy conservation developments. The program, initiated during this year-long period, consists of a series of tasks integrating and supporting energy storage implementation. Program management and technical coordination activities monitor the wide range of research ongoing both under government support and in industry and provide a locus for dissemination of results. Recently completed DOE demonstration studies provide the central data base and the DOE CAES and UPH Technology Program activities provide another major ...
1982-06-01
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.
FFTF reactor-characterization program: gamma-ray measurements and shield characterization
A series of experiments is to be made during the acceptance test program of the Fast Flux Test Facility (FFTF) to measure the gamma ray characteristics of the Fast Test Reactor (FTR) and to establish the performance characteristics of the reactor shield. These measurements are a part of the FFTF Reactor Characterization Program (RCP). Detailed plans have been developed for these experiments. During the initial phase of the Characteristics Program, which will be carried out in the In-Reactor Thimble (IRT), both active and passive measurement methods will be employed to obtain as much information concerning the gamma ray environment as is practical. More limited active gamma ray measurements also will be made in the Vibration Open Test Assembly (VOTA).
Energy Technology Data Exchange (ETDEWEB)
This report describes the research conducted in the High Energy Physics Division of Argonne National Laboratory during the period of July 1, 1992--December 30, 1992. Topics covered here include experimental and theoretical particle physics, advanced accelerator physics, detector development, and experimental facilities research. Lists of division publications and colloquia are included.
1993-07-01
Energy Technology Data Exchange (ETDEWEB)
This report describes the research conducted in the High Energy Physics Division of Argonne National Laboratory during the period of January 1, 1993--June 30, 1993. Topics covered here include experimental and theoretical particle physics, advanced accelerator physics, detector development, and experimental facilities research. Lists of division publications and colloquia are included.
1993-12-01
Energy Technology Data Exchange (ETDEWEB)
This document defines analytical services the Waste Sampling and Characterization Facility (WSCF) shall provide the Environmental Compliance Program (ECP) throughout calendar year (CY) 2000. Two organizations within ECP are responsible for monitoring liquid and gaseous effluents and the environment immediately around facilities that contain or may contain radioactive and hazardous materials. Monitoring & Reporting (M&R), of Fluor Hanford Environmental Services, is responsible for effluent monitoring data, and Environmental Monitoring & Investigations (EMI), of Waste Management Technical Services, Inc., for near-facility environmental monitoring data. These organizations serve numerous projects, some of which are managed by other companies such as CH2M HILL and Bechtel Hanford, Inc. Monitoring data are collected and evaluated to determine their state of compliance with applicable federal ...
2000-06-01
Radiation hardening of diagnostics
International Nuclear Information System (INIS)
The world fusion program has advanced to the stage where it is appropriate to construct a number of devices for the purpose of burning DT fuel. In these next-generation experiments, the expected flux and fluence of 14 MeV neutrons and associated gamma rays will pose a significant challenge to the operation and diagnostics of the fusion device. Radiation effects include structural damage to materials such as vacuum windows and seals, modifications to electrical properties such as electrical conductivity and dielectric strength and impaired optical properties such as reduced transparency and luminescence of windows and fiber optics during irradiation. In preparation for construction and operation of these new facilities, the fusion diagnostics community needs to work with materials scientists to develop a better understanding of radiation effects, and to undertake a testing program aimed at developing workable solutions for ...
Reactor physics results from fast flux test facility operation
International Nuclear Information System (INIS)
Criticality was first achieved with the Fast Flux Test Facility (FFTF) a little more than 10 yr ago on February 9, 1980. Although the FFTF was designed and built primarily for testing fuels, materials, and components for the liquid-metal fast breeder reactor program, it has, over its first 10 yr of operation, provided valuable information in many other areas. This paper provides a summary of the contributions to the physics of liquid-metal reactors (LMRs) obtained from operation of and testing in the FFTF, with emphasis on some of the more significant and interesting accomplishments.
1990-11-11
FFTF (Fast Flux Test Facility) Reactor Characterization Program: Absolute Fission-rate Measurements
Energy Technology Data Exchange (ETDEWEB)
Absolute fission rate measurements using modified National Bureau of Standards fission chambers were performed in the Fast Flux Test Facility at two core locations for isotopic deposits of {sup 232}Th, {sup 233}U, {sup 235}U, {sup 238}U, {sup 237}Np, {sup 239}Pu, {sup 240}Pu, and {sup 241}Pu. Monitor chamber results at a third location were analyzed to support other experiments involving passive dosimeter fission rate determinations.
1981-05-01
FFTF (FAST FLUX TEST FACILITY) REACTOR CHARACTERIZATION PROGRAM ABSOLUTE FISSION RATE MEASUREMENTS
Energy Technology Data Exchange (ETDEWEB)
Absolute fission rate measurements using modified National Bureau of Standards fission chambers were performed in the Fast Flux Test Facility at two core locations for isotopic deposits of {sup 232}Th, {sup 233}U, {sup 235}U, {sup 238}U, {sup 237}Np, {sup 239}Pu, {sup 240}Pu, and {sup 241}Pu. Monitor chamber results at a third location were analyzed to support other experiments involving passive dosimeter fission rate determinations.
1981-05-01
End user needs for enhanced IAEA Safeguards Information Management Capabilities
International Nuclear Information System (INIS)
The International Atomic Energy Agency is undertaking a program for strengthening its safeguards on the recognition that safeguards must give assurance not only of the non-diversion of declared material or that declared facilities are not being misused, but also of the absence of any undeclared nuclear activities in States which have signed comprehensive safeguards agreements with the Agency. The IAEA has determined that the detection of undeclared nuclear activities and the creation of confidence in the continuing peaceful use of declared material and facilities is largely dependent on more information being made available to the Agency and on the capability of the Agency to make more effective use of this additional information, as well as existing information.
International Nuclear Information System (INIS)
In this study the results of mathematical simulation and experimental research of texture transition in stress assisted shear phase transformations are discussed. The orientation distribution function (ODF) calculation model to the any type crystalline lattice symmetry materials has been suggested. By crystalline lattice symmetry analysis this computer program determines necessary amount of the initial experimental data. The experimental verification supports this model well. The ODF calculation model after shear phase transformation with equal use of all possible variants of orientation relationship or with various degrees of variant selection worked out. In this study the experimental and calculating data of the direct and reversal shear transformations #alpha# <=> #gamma# in Fe-alloys and B2 <=> B19' in Ti-Ni alloys are discussed. The stress assisted shear phase ...
Monte Carlo simulations and experimental validations of #alpha# eigenvalues - 091
International Nuclear Information System (INIS)
A Monte Carlo method called transient curve fitting method was developed to calculate a eigenvalues by first simulating the existing neutrons and precursors in the system, then calculating the Eigen-distribution of neutron flux and calculating the a eigenvalues using the transient results based on the Eigen-distribution by the code TMCC. The results of this method are tested by calculating Godiva Benchmark problems and they agree well with the benchmark results. Then the reasonable results of Subcritical Facility in Tsinghua University are given by TMCC, and the results are compared with the experimental results measured by Rossi-a method. Even in the deep subcritical cases, the method can give results consistent with experimental results. (authors)
2010-05-09
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 ...
1985-11-01
Energy Engineering Analysis Program, Limited Energy Study, Fort Hunter-Liggett, California. Volume I
This report summarizes all work of the Limited Energy Study, Energy Engineering Analysis Program (EEAP), Fort Hunter Liggett, California, authorized under Contract Number DACA05-92-C-0155 with the U.S. Army Corps of Engineers, Sacramento District, California. The purpose of this study is to develop projects and actions that will reduce facilities energy consumption and operating costs at Fort Hunter Liggett. Implementation of these projects will contribute to achieving the goal of the Army Facilities Energy Plan of a reduction in energy consumption per square foot of building floor area of 20 percent by FY2000 from FY1985 baseline levels.
1993-07-01
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 operations are discussed.
1982-09-01
British Library Electronic Table of Contents (United Kingdom)
The influence of geometry and operating conditions of the centrifugal compressor stage on the radial gas force is determined on the basis of the theoretical method and calculation program using experimental boundary conditions.
2011-01-01
Development of Mainshaft High Speed Cylindrical Roller Bearings for Gas Turbine Engines.
This combined analytical and experimental program is aimed at generating a manual that will permit the design of 3.0 MDN cylindrical roller bearings. The roller bearing analysis will be correlated with the results from a series of bearing tests designed t...
1977-01-01
How does one develop the right quality assurance program for waste management projects?
International Nuclear Information System (INIS)
The quality assurance requirements in use today for radioactive waste facilities, geologic repositories and hazardous waste projects were developed initially for the nuclear power plant industry, and their intent is being applied by regulations and guidance documents to radioactive and hazardous waste programs. The wording of the NRC quality assurance requirements in Appendix B of 10CFR50, the related guidance documents and the industry's ANSI/ASME NQA-1 were developed over a period of several years to address quality assurance for the design and construction of the complex and interactive systems to produce electrical power using nuclear fuel. Now, those same documents are the basis for the quality assurance requirements and guidance for waste management facilities and repositories. The intent of Appendix B of 10CFR50 and NQA-1 can easily be applied to waste projects, providing one understands and uses the intent of the ...
1988-10-03
FFTF operations: initial operator training simulator program
International Nuclear Information System (INIS)
This paper describes the Fast Flux Test Facility (FFTF) Operations initial training program utilizing the Operator Training Simulator (OTS). The OTS is a computer-driven system that provides real time response of essential FFTF plant functions to a control room mockup. The FFTF, a 400 Megawatt, three-loop, sodium-cooled fast test reactor will test fuels, materials and equipment for the U.S. Liquid Metal Fast Breeder Reactor Program. Construction is expected to be completed in August 1978. Initial criticality is expected in early 1979. This schedule will require FFTF control room operators to be fully qualified to operate the facility by late 1979. Because FFTF is like no other U.S. nuclear reactor, existing U.S. utility plants could not be depended on to provide highly experienced people to operate FFTF. Therefore, an Operator Training Simulator has been built. The OTS will play a vital role in the ...
Energy Technology Data Exchange (ETDEWEB)
This report describes the status of nuclear safety and radiation protection in the facilities of the AREVA group and gives information on radiation protection in the service operations, as observed through the inspection programs and analyses carried out by the General Inspectorate in 2007. Having been submitted to the group's Supervisory Board, this report is sent to the bodies representing the personnel. Content: 1 - A look back at 2007 by the AREVA General Inspector: Visible progress in 2007, Implementation of the Nuclear Safety Charter, Notable events; 2 - Status of nuclear safety and radiation protection in the nuclear facilities and service operations: Personnel radiation protection, Event tracking, Service operations, Criticality control, Radioactive waste and effluent management; 3 - Performance improvement actions; 4 - Description of the General Inspectorate; 5 - Glossary.
2007-07-01
Energy Technology Data Exchange (ETDEWEB)
The Savannah River Site disposes of low-level radioactive waste within on-site engineered disposal facilities. The Savannah River Site must demonstrate that these disposals meet the requirements of DOE Order 435 . 1 through a process known as performance assessment (PA). The objective of this document is to provide the radionuclide -specific data needed for the PA calculations . This work is part of an on-going program to periodically review and update existing PA work as new data becomes available. Revision of the E -Area Low-Level Waste Facility PA is currently underway. The number of radionuclides selected to undergo detailed analysis in the PA is determined by a screening process. The basis of this process is described. Radionuclide-specific data for half-lives, decay modes, daughters, dose conversion factors and groundwater concentration limits are presented with source references and methodologies.
2007-03-20
Energy Technology Data Exchange (ETDEWEB)
The Buried Waste Integrated Demonstration (BWID) is a program of the Department of Energy (DOE) Office of Technology Development whose mission is to evaluate different new and existing technologies and determine how well they address DOE community waste remediation problems. Twenty-three Technical Task Plans (TTPs) have been identified to support this mission during FY-92; 10 of these have identified some support requirements when demonstrations take place. Section 1 of this report describes the tasks supported by BWID, determines if a technical demonstration is proposed, and if so, identifies the support requirements requested by the TTP Principal Investigators. Section 2 of this report is an evaluation identifying facility characteristics of existing Idaho National Engineering Laboratory (INEL) facilities that may be considered for use in BWID technology demonstration activities.
1992-04-01
Coal-liquefaction-process research quarterly report, January 1 - March 31, 1982
Objectives of the program are to understand the mechanisms of coal liquefaction, to determine the role of catalysts in the direct conversion of coal to liquids, to determine the mechanism of catalyst deactivation and to explore slurry phase catalyst systems. Specific projects include: short-contact time coal liquefaction, mineral matter effects and catalyst studies. During this period, work was performed on: (1) the stability, at reaction temperature, of a recycle solvent obtained from the Lummus Two Stage Liquefaction facility, (2) reactions of preasphaltenes and asphaltenes prepared under various reaction severities, (3) the evaluation of the catalyst level detector installed at the H-Coal facility, (4) the characterization of oil soluble metal compounds with respect to hydrogenation activity, and (5) characterization, deactivation and regeneration of catalysts obtained from both the H-Coal and Lummus ...
1982-10-01
Experimental and analytical studies of four-inch pipe whip tests under PWR LOCA conditions
Energy Technology Data Exchange (ETDEWEB)
In the tests, the effects of the overhang length on the pipe whip behavior of the pipe-restraints system were studied by measuring the strains and deformations of the test pipe and restraints, and the restraints forces. The equation for predicting the maximum strain at the outer surface of the pipe was derived using a static equilibrium condition. The calculated maximum strains at the outer surface of the pipe agree fairly well with experimental data. The dynamic response analysis of the pipe-restraints system was conducted by the finite element program ADINA. The applicability of the ADINA program to the pipe whip analysis is made clear through this analysis.
1984-01-01
International Nuclear Information System (INIS)
The Mixed Waste Management Facility, or MWMF, has been proposed as a national testbed facility for the demonstration and evaluation of technologies that are alternatives to incineration for the treatment of mixed low-level waste. The facility design will enable evaluation of technologies at pilot scale, including all aspects of the processes, from receiving and feed preparation to the preparation of final forms for disposal. The MWMF will reduce the risk of deploying such technologies by addressing the following: (1) Engineering development and scale-up. (2) Process integration and activation of the treatment systems. (3) Permitting and stakeholder issues. In light of the severe financial constraints imposed on the DOE and federal programs, DOE/HQ requested a study to assess the cost benefit for the MWMF given other potential alternatives to meet waste treatment needs. The MVVMF Project was asked to ...
2005-10-01
International Nuclear Information System (INIS)
Full text: Founded in 1964, Ankara Nuclear Research and Training Center (ANRTC) conducts and facilitates the scientific activities including training (summer practice, MSc and Ph D studies in physics and chemistry, IAEA fellowship programs etc.), research and other studies in nuclear and related fields. As it's a part of main duties, ANRTC has analysis on the variety of samples, and radiation protection services commercially, for radiation workers in state, public and private sectors. Research, development and application projects implemented in this Center have mostly been supported by State Planning Organization (SPO) and Turkish Atomic Energy Authority (TAEA). In addition to the projects there are on going collaborative studies with some national Universities and International Atomic Energy Agency. The main activities carried out in ANRTC can be summarized as: studies on experimental nuclear physics, application of nuclear techniques such as ...
2004-10-01
The European Dioxin Emission Inventory. Stage II. Final report
Energy Technology Data Exchange (ETDEWEB)
For Stage II of the European Dioxin Project the following objectives were set: - Amendment of existing emission data collected for most relevant emission sources in order to reduce uncertainties of emission estimates. Collecting first emission data from countries not yet performing dioxin emission measurement programs. Extending the inventory of dioxin emissions to ambient air produced in Stage I by a complementary study on emissions to land and water. Extending the regional scope of data collection to countries in Central Europe. The report of Stage II of the European Dioxin Project is presented in 3 Volumes. Volume 1 contains an overview on the background and approach of different activities carried out and on the results obtained. These results are put into a broader view regarding the dioxin reduction measures in Europe leading to conclusions and recommendation for future work. Volume 2 of the report contains a detailed presentation of the sub-projects carried ...
2001-07-01
Electron-beam-plasma ion source as source of negative fluorine
Energy Technology Data Exchange (ETDEWEB)
Radioactive ion beams (RIBs) of short-lived isotopes of fluorine are in demand for investigating astrophysical phenomena related to the hot CNO cycle and rp processes responsible for stellar nucleosynthesis. Since negative ion beams are required for injection into tandem electrostatic accelerators, such as the 25 MV tandem accelerator used for post acceleration of RIBs for the Holifield Radioactive Ion Beam Facility (HRIBF) research program at the Oak Ridge National Laboratory (ORNL), efficient, direct-formation F{sup -} ion sources are highly desirable for RIB applications involving this type of post-accelerator. We have conceived and evaluated a direct extraction F{sup -} source for potential RIB applications which is predicated on the reverse polarity operation of a positive electron-beam-plasma target/ion source (EBPTIS) while simultaneously feeding fluorine rich compounds and Cs vapor into the source. The source is found to operate in two ...
1997-11-01
Charge and fluence lifetime measurements of a dc high voltage GaAs photogun at high average current
Energy Technology Data Exchange (ETDEWEB)
GaAs-based dc high voltage photoguns used at accelerators with extensive user programs must exhibit long photocathode operating lifetime. Achieving this goal represents a significant challenge for proposed high average current facilities that must operate at tens of milliamperes or more. This paper describes techniques to maintain good vacuum while delivering beam, and techniques that minimize the ill effects of ion bombardment, the dominant mechanism that reduces photocathode yield of a GaAs-based dc high voltage photogun. Experimental results presented here demonstrate enhanced lifetime at high beam currents by: (a) operating with the drive laser beam positioned away from the electrostatic center of the photocathode, (b) limiting the photocathode active area to eliminate photoemission from regions of the photocathode that do not support efficient beam delivery, (c) using a large drive laser beam to distribute ion damage ...
2011-04-01
Energy Technology Data Exchange (ETDEWEB)
The high-purity-oxygen activated sludge process will be used to expand secondary treatment capacity and improve water quality in Santa Monica Bay. The facility is operated by the city of Los Angeles Department of Public Works` Bureau of Sanitation. The overall Hyperion Full Secondary Project is 30% complete, including a new headworks, a new primary clarifier battery, an electrical switch yard, and additional support facilities. The upgrading of secondary facilities is 50% complete, and construction of the digester facilities, the waste-activated sludge thickening facility, and the second phase of the three-phase modification to existing primary clarifier batteries has just begun. The expansion program will provide a maximum monthly design capacity of 19,723 L/s(450 mgd). Hyperion`s expansion program uses industrial treatment techniques ...
1993-09-01
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
Energy Technology Data Exchange (ETDEWEB)
Contract No. DACA 90-8l-C-oo72 directs that a basewide energy study be accomplished for the Mannheim and Pirmasens Military Communities, Federal Republic of Germany. The project is identified as Energy Engineering Analysis Program (EEAP) Package No. 5. The overall objective of the study is to produce a systematic plan of improvement projects that will reduce by 1985 the energy consumption in compliance with the Army Facilities Energy Plan without decreasing the readiness posture of the Army.
1984-05-01
Status of neutron cross sections for reactor dosimetry
International Nuclear Information System (INIS)
The status of neutron activation cross sections for some threshold reactions important for reactor materials dosimetry is reviewed. An attempt is made to understand and explain discrepancies between integral and differential data, using recent available experimental results. The importance of standard and benchmark neutron fields for testing differential data for reactor dosimetry is emphasized and the Interlaboratory Reaction Rate (ILRR) program, as well as a similar program pursued by the IAEA, are briefly described.
1976-07-06
Free-electron lasers and related topics
Energy Technology Data Exchange (ETDEWEB)
This past year has been very exciting for the experimental free-electron laser (FEL) programs. At three Laboratories, oscillator experiments were performed with wavelengths from the visible to far infrared. The output powers are steadily advancing. The status of these programs will be discussed. As shorter wavelengths and higher powers are pursued, higher currents with improved beam quality will be required. Advanced electron linacs should be developed to meet these demands. 13 references, 5 figures, 3 tables.
1984-01-01
The ANL X6B beamline at NSLS: A versatile facility
Energy Technology Data Exchange (ETDEWEB)
We have described the x-ray optics and beamline performance of the ANL X6B beam line at the NSLS. Considerable flexibility has been built into the beam line to accommodate a wide range of x-ray diffraction, scattering, and spectroscopy experiments with various requirements. We presented selected examples of experimental results and showed that with the high intensity, high energy resolution, high-q resolution, and energy tunability, the X6B beam line has become a versatile facility.
1994-07-01
Preliminary Study of Plasma Stream Interaction with Tungsten Target within RPI-IBIS Facility
International Nuclear Information System (INIS)
The paper presents results of experimental research on the interaction of a pulsed plasma-ion stream with a tungsten (W) target. The pulsed hydrogen plasma was produced within the RPI-IBIS (Multi-Rod Plasma Injector) facility at IPJ in Swierk. Measurements were carried out by means of optical spectroscopy and corpuscular diagnostic techniques. For experiments with the W-target the operational conditions (so-called PID mode) were chosen when a clean hydrogen plasma stream was generated. Attention was paid to the identification of WI and WII spectral lines.
2006-01-01
Multi-frequency binary sequence testing at FFTF [Fast Flux Test Facility
International Nuclear Information System (INIS)
The multi-frequency binary sequence experimental technique has been implemented at the Fast Flux Test Facility for routine surveillance activities. The frequency content of the standard rod-movement sequence has been shown to be sufficient to normalize the data at moderate frequencies. This obviates the need for auxiliary calibration measurements and provides the reactivity worth of the test control rod. Analyses of a series of tests conducted in 1986 illustrate that the rod worths inferred from the tests are consistent with zero-power measurements. Also, the dependence of the prompt feedback time constant on reactor conditions was determined.
1988-09-18
Hydrogen flame acceleration and transition to detonation
Energy Technology Data Exchange (ETDEWEB)
This paper describes the results obtained from two large experimental facilities built at Sandia National Laboratories in Albuquerque, NM. FLAME (Flame Acceleration Measurements and Experiments) is a large horizontal rectangular channel designed to study flame acceleration, transition to detonation, simulation of combustion in containment geometries, component heating, and other problems in hydrogen combustion relevant to reactor safety. The Heated Detonation Tube has been designed to study detonations in hydrogen-air-steam mixtures. Both facilities have been in operation for just over a year. 12 figures.
1984-01-01
Hydrogen flame acceleration and transition to detonation
International Nuclear Information System (INIS)
This paper describes the results obtained from two large experimental facilities built at Sandia National Laboratories in Albuquerque, NM. FLAME (Flame Acceleration Measurements and Experiments) is a large horizontal rectangular channel designed to study flame acceleration, transition to detonation, simulation of combustion in containment geometries, component heating, and other problems in hydrogen combustion relevant to reactor safety. The Heated Detonation Tube has been designed to study detonations in hydrogen-air-steam mixtures. Both facilities have been in operation for just over a year. 12 figures.
1984-10-23
Forthcoming (n, #gamma#) measurements on the Fe and Ni isotopes at CERN n_TOF
International Nuclear Information System (INIS)
An overview of the past, present and future research activities at the CERN neutron time of flight facility n_TOF is given, with special focus on the astrophysical aspects. During the first campaign (Phase I), neutron capture cross sections of relevance for several aspects of the s-process nucleosynthesis have been measured. A second campaign has recently started (Phase II), aiming at the study of the weak s-process component via accurate (n,#gamma#) measurements of the Fe and Ni isotopes. Some changes in the facility will allow us to perform these measurements with improved experimental conditions.
2010-01-01
The application of virtual instruments technique in U-H_2 experimental system
International Nuclear Information System (INIS)
The concept of the modern data acquisition system and some functional specialties of the programming software--Visual Basic 6.0 are introduced. The construction and theory of the hardware and the designing principle of the software are described. Experimental results showed that the real-time data acquisition rate was as high as 10 times per second in the system. And the relative standard uncertainty of the measurement was less than 0.5%. (authors)
2004-11-01
Energy Technology Data Exchange (ETDEWEB)
A summary is provided of the first of three years of experimental and theoretical research on free-forced convection flows in cavity-type solar receivers. New experimental and theoretical results are presented and discussed. The implication of these findings, with respect to the future thrust of the research program, is clarified as well as is possible at the present time. Following various related conclusions a summary and tentative schedule of work projected for year two of research are presented.
1982-01-01
National Ignition Facility Incorporates P2/E2 in Aqueous Parts Cleaning of Optics Hardware
Energy Technology Data Exchange (ETDEWEB)
When completed, Lawrence Livermore National Laboratory's (LLNL) National Ignition Facility (NIF) will be the world's largest laser with experimental capabilities applicable to stockpile stewardship, energy research, science and astrophysics. As construction of the conventional facilities nears completion, operations supporting the installation of specialized laser equipment have come online. Playing a critical role in the precision cleaning of mechanical parts from the NIF beamline are three pieces of aqueous cleaning equipment. Housed in the Optics Assembly Building (OAB), adjacent to NIF's laser bay, are the large mechanical parts gross cleaner (LMPGC), the large mechanical parts precision cleaner (LMPPC), and the small mechanical parts gross and precision cleaner (SMPGPC). These aqueous units, designed and built by Sonic Systems, Inc., of Newtown, Pennsylvania, not only accommodate parts that ...
2001-07-27
Two microcomputer programs for evaluating truck haulage systems in surface mines
Energy Technology Data Exchange (ETDEWEB)
Truck haulage systems are widely used in open pit mining operations. Thanks to the rapid development and use of personal computers, simulation of haulage systhems involving Computer Aided Design (CAD) facilities and animation has recently become an attractive alternative in the Swedish Mining Industrie compared to the conventional simulations. Furthermore, when planning or simulating hauling operations, it is important to be able to accurately calculate velocities, cycle times and fuel consumption for truck fleets under varying conditions. It is the objective of this paper to present the basic features and principles of two microcomputer programs, TRUCKPER and METAFORA. These programs can be used as an integrated tool for evaluating truck haulage systems in surface mines. (orig.).
1990-01-01
The kWh model finds the kWh outputs of each plant and reservoir capacities of hydro and pumped storage plants and minimizes the sum of fixed charges for constructing the reservoirs and generating facilities, also the fuel costs of thermal and nuclear plants. It is a linear programming problem whose constants are represented by nonlinear functions of kW running capacity of each plant. The optimal pattern of nuclear and thermal units is found by solving the linear programming problem derived for the pumped storage and hydroplants. Excluding the upper bound constraints, the number of constraint equations are few and do not increase with the number of units, although the number of variables increases. The computing time increases only in proportion to the number of groupings of generating units. Sensitivity analysis can be done easily. The detailed operational behavior of each generating unit can be taken into account.
1979-03-01
FFTF reactor characterization program
International Nuclear Information System (INIS)
Preparations are under way for the initial startup and testing of the Fast Flux Test Facility (FFTF). The FFTF Reactor Characterization Program is that part of the startup test plan that deals with the determination of the neutron, gamma ray and thermal hydraulic characteristics of the reactor. This program encompasses measurements and calculations of: neutron spectra, flux and fluence; gamma-ray spectra, dose and heating; fission rate distributions; capture rate distributions; other reaction rates of interest; fission product yields; and thermal hydraulic data. Measurements of these parameters will be made in the reactor core and reflectors, will extend vertically downward to the vicinity of the core support structure and upward to the top of the sodium pool, and will extend radially outward to include in-vessel fuel storage locations and the cavity between the reactor vessel and the concrete wall.
Brookhaven National Laboratory Coastal Meteorology Program, 1972-1983
Energy Technology Data Exchange (ETDEWEB)
Research conducted at Brookhaven National Laboratory under the Coastal Meteorology and Diffusion Research Program from 1972 to 1983 is summarized by the following study areas: Diffusion Studies, Boundary Layer Studies, Coastal Meteorology Studies, Air-Sea Interaction Studies, Coastal Transport and Diffusion Climatology, Seabreeze Modeling and Instrument Development, all supported by the US Department of Energy. Studies supported by the Nuclear Regulatory Commission, the National Science Foundation and the American Petroleum Institute are also described. A summary of a Workshop on Coastal Atmospheric Transport Processes, an account of studies in progress, recommendations for future research and a description of facilities and instrumentation available are also included. A list of all publications and presentations prepared as part of the program is given with abstracts. 7 figures, 1 table.
1983-06-01
Summary of Initial Testing of SuperLig 644 at the TFL Ion Exchange Facility
Energy Technology Data Exchange (ETDEWEB)
Research at the Savannah River Technology Center aided development of a technical design basis for a Waste Treatment Plant (WTP) to pre-treat and vitrify Hanford tank waste as part of the River Protection Project (RPP). The research addresses safety concerns, process optimization, and waste form compliance. This program will provide technical data to ensure that the process functions as it was designed and minimizes costs.
2001-04-17
Snake River Sockeye Salmon Habitat and Limnological Research; 1995 Annual Report.
Energy Technology Data Exchange (ETDEWEB)
This report contains studies which are part of the Bonneville Power Administration`s program to protect, mitigate, and enhance fish and wildlife affected by the development and operation of hydroelectric facilities on the Columbia River and its tributaries. Attention is focused on population monitoring studies in the Sawtooth Valley Lakes. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database.
1996-05-01
Pacific Northwest Laboratory Maintenance Implementation plan
Energy Technology Data Exchange (ETDEWEB)
This Maintenance Implementation plan has been developed for Pacific Northwest Laboratory's (PNL) Nuclear Facilities: 306W, 324, 325, 327 and 329NMF. It is based on a graded approach, self-assessment of the existing maintenance program(s) per the requirements specified by US Department of Energy (DOE) Order 4330.4A, Chapter II, Change {number sign}3. The results of this assessment were evaluated to determine needed improvements in PNL Craft Services' current maintenance program. The objective of this implementation plan is to provide baseline information for compliance to the DOE 4330.4A, and for needed improvements. The prime consideration in applying a graded approach to the Order has been to maintain safe and reliable operations, environmental compliance, safeguards and security, programmatic mission, facility preservation, and/or other facility-specific ...
1992-06-01
Pacific Northwest Laboratory Maintenance Implementation plan
Energy Technology Data Exchange (ETDEWEB)
This Maintenance Implementation plan has been developed for Pacific Northwest Laboratory`s (PNL) Nuclear Facilities: 306W, 324, 325, 327 and 329NMF. It is based on a graded approach, self-assessment of the existing maintenance program(s) per the requirements specified by US Department of Energy (DOE) Order 4330.4A, Chapter II, Change {number_sign}3. The results of this assessment were evaluated to determine needed improvements in PNL Craft Services` current maintenance program. The objective of this implementation plan is to provide baseline information for compliance to the DOE 4330.4A, and for needed improvements. The prime consideration in applying a graded approach to the Order has been to maintain safe and reliable operations, environmental compliance, safeguards and security, programmatic mission, facility preservation, and/or other facility-specific requirements. Using the ...
1992-06-01
Coal liquefaction. Quarterly report, January--March 1976
ERDA's coal liquefaction program is reviewed, especially the progress with several pilot plant operations. Other items involve the possible recovery of organic chemicals from coal liquids, the filtration of coal liquids, some experiments on hydrogenation and carbonization, and renovation of the Cresap materials and equipment test facility. (LTN)
1976-01-01
Energy Technology Data Exchange (ETDEWEB)
The Atlantic Wind Test Site was established in 1980 as a laboratory to facilitate the evaluation and demonstration of wind energy systems and equipment. This annual report describes its organization and management, facilities, major projects, and the outlook for the future. Major projects include wind diesel; AWTS-IREQ collaboration; remote community data acquisition; lagerwey test program; Alaska Energy Authority Project; public education; Atlantic Orient Corporation 15/50 Project; and the soft VAWT project.
1994-12-31
Energy Technology Data Exchange (ETDEWEB)
A thermohydraulic study of MTR fuel element is presented as a basic requirement for the development of an irradiation facility for testing fuel elements. A computer code named 'Thermo' has been developed for this purpose, which can stimulate different working conditions, such as, cooling, power elements and neutron flux, performing all pertinent thermohydraulic calculations. Thermocouples were used to measure the temperature gradients of the cooling fluid throughout the IEAR-1 reactor core. All experimental data are in good agreement with the theoretical model applied in this work. Finally, a draft of the proposed facility and its safety system is presented. (author)
1980-07-01
The {sup 234}U neutron capture cross section measurement at the n TOF facility
Energy Technology Data Exchange (ETDEWEB)
The neutron capture cross-section of {sup 234}U has been measured for energies from thermal up to the keV region in the neutron time-of-flight facility n-TOF, based on a spallation source located at CERN. A 4{pi} BaF{sub 2} array composed of 40 crystals, placed at a distance of 184.9 m from the neutron source, was employed as a total absorption calorimeter (TAC) for detection of the prompt {gamma}-ray cascade from capture events in the sample. This text describes the experimental setup, all necessary steps followed during the data analysis procedure. Results are presented in the form of R-matrix resonance parameters from fits with the SAMMY code and compared to the evaluated data of Endf in the relevant energy region, indicating the good performance of the n-TOF facility and the TAC. (authors)
2008-07-01
Industrial applications of the Jefferson Lab high-power free-electron laser
International Nuclear Information System (INIS)
In partnership with the US Navy, high-technology corporations, and research universities, Jefferson Lab is building a superconducting radio-frequency (SRF) accelerator-driven free-electron laser (FEL) and is outfitting an FEL user facility. This first fourth-generation light source - a 1 kW, 3 #mu#m infrared (IR) laser - is the first step in a program to develop high-average-power SRF-based IR and ultraviolet (UV) FELs for multiple manufacturing applications as well as for defense-related applied research and basic scientific research. This initial FEL will be driven by a 42 MeV, 5 m A recirculating SRF linac similar to the much larger SRF linac in Jefferson Lab's 4 GeV, 200 #mu#A Continuous Electron Beam Accelerator Facility (CEBAF). The FEL is expected to demonstrate 75% energy recovery. Its linac will be cooled by the existing CEBAF cryogenic system. At Jefferson Lab, an infrastructure of facilities ...
1998-09-02
Experimental and analytical studies of four-inch pipe whip tests under PWR LOCA conditions
Energy Technology Data Exchange (ETDEWEB)
This paper presents experimental and analytical results of pipe whip tests performed under PWR LOCA conditions using a test pipe of 4-inch diameter and U-shaped restraints. In the tests, the effects of the overhang length on the pipe whip behavior of the piperestraints system were studied by measuring the strains and deformations of the test pipe and restraints, and the restraints forces. The equation for predicting the maximum strain at the outer surface of the pipe was derived using a static equilibrium condition. The calculated maximum strains at the outer surface of the pipe agree fairly well with experimental data. The dynamic response analysis of the pipe-restraints system was conducted by the finite element program ADINA. The applicability of the ADINA program to the pipe whip analysis is made clear through this analysis.
1984-01-01
A study on the experimental verification for the pipe whip problem in a Nuclear Power Plant
Energy Technology Data Exchange (ETDEWEB)
The purpose of this study is to investigate on the experimental verification analysis for the pipe whip problems and to obtain the quantitative evaluation technologies for the design technique of pipe whip restraints. These will contribute to the advance of nuclear regulatory technologies and enhance nuclear power plant safety. This study presents the experimental and transient analytical results of pipe whip tests using the 4', 6' diameter pipe and U-shaped restraints. In the tests, the effects of the overhang length, clearance, impact height on the pipe whip behavior of the pipe-restraints were investigated. The transient impact analysis of the pipe-restraint system was conducted by the finite element program ABAQUS. The applicability of the ABAQUS program to the pipe whip analysis is made clear through this analysis.
1993-12-15
Experimental modelling of thermal consolidation effects around a high level waste repository
International Nuclear Information System (INIS)
This report summarizes the results of a research programme which involves the development of a laboratory experimental facility for the simulation and study of hydro-thermo-mechanical processes in saturated geomaterials with low permeability. The experimentation involves a synthetic cement based porous material made of cement grout which possesses permeabilities in the range of dense unfractured sandstones or shale. Specially manufactured pore-pressure transducers were installed within the cylindrical block at locations adjacent to a plane free boundary. The block was saturated with the periodic application of a vacuum. In its saturated state the plane boundary of the block was subjected to heating via a circular heater the temperature of which was maintained constant. The resulting pore pressure generation along with temperature at these locations was monitored continuously. The results of a series of experiments are ...
Reduction of statistic error in Mihalczo subcriticality measurement
Energy Technology Data Exchange (ETDEWEB)
The theoretical formula for the statistical error estimation in Mihalczo method was derived, and the dependence of the error were investigated on the facility to be measured and on the parameter in the data analysis. The formula was derived based on the reactor noise theory and the error theory for the frequency analysis, and found that the error depends on such parameters as the prompt neutron decay constant, detector efficiencies, and the frequency bandwidth. Statistical errors estimated with the formula was compared with experimental values and verified to be reasonable. Through parameter surveys, it is found that there is an optimum combination of the parameters to reduce the magnitude of the errors. In the experiment performed in DCA subcriticality measurement facility, it is estimated experimentally that the measurement requires 20 minutes to obtain the statistic error of 1% for the keff 0.9. ...
1998-08-01
Flux enhancement options for an LEU-fueled MIT reactor
International Nuclear Information System (INIS)
The Monte-Carlo transport code MCNP was used to evaluate possible arrangements of cores for the MIT Reactor using monolithic LEU fuel. Plate and moderator thicknesses were varied, and fixed absorbers and inner reflectors added in an effort to maximize available neutron fluxes at in-core and ex-core locations of experimental facilities. Addition of D_2O in the H_2O moderator was also evaluated. Comparisons of the fast, epithermal, and thermal fluxes were made at selected locations. Keff was also evaluated and critical blade heights compared with the existing HEU core. Results indicate that the LEU fluxes could approach HEU values with the use of a fueled in-core experimental facility, a fixed boron absorber spider and an inner beryllium reflector. (author)
2004-11-07
Programming resistive switching memory by a charged capacitor
British Library Electronic Table of Contents (United Kingdom)
Resistive switching memory is a very promising technology for emerging nonvolatile memory applications. Generally, the switching behavior is triggered by a sweep or pulse voltage. In this paper, a charged capacitor is proposed to be used as the external electrical source to program a resistive switching element. From theoretical analyses based on a set behavior model, the capacitor approach can program the device efficiently. Compared with sweep or pulse mode, capacitor driving method can greatly reduce over-programming after the set event, and thus improve the resistance uniformity. The experimental results performed on Cu/ZrO2:Cu/Pt device support this conclusion quite well. The proposed methodology has great value for achieving a reliable resistive switching, which is important for high...
2011-01-01
International Nuclear Information System (INIS)
The US Department of Energy has provided support to four universities and the Oak Ridge National Laboratory in order to pursue research leading to the development and deployment of an advanced robotic system capable of performing tasks that are hazardous to humans, that generate significant occupational radiation exposure, and/or whose execution times can be reduced if performed by an automated system. The goal is to develop a generation of advanced robotic systems capable of performing surveillance, maintenance, and repair tasks in nuclear facilities and other hazardous environments. This goal will be achieved through a team effort among the Universities of Florida, Michigan, Tennessee, Texas, and the Oak Ridge National Laboratory, and their industrial partners, Combustion Engineering, Martin Marietta Baltimore Aerospace, Odetics, Remotec, and Telerobotics International. Each of the universities and ORNL have ongoing activities and corresponding ...
The Oak Ridge Y-12 Plant biological monitoring and abatement program for East Fork Poplar Creek
Energy Technology Data Exchange (ETDEWEB)
In May 1985, a National Pollutant Discharge Elimination System permit was issued for the Oak Ridge Y-12 Plant, a nuclear weapons components production facility located in Oak Ridge, Tennessee, and operated by Martin Marietta Energy Systems, Inc., for the US Department of Energy. As a condition of the permit, a Biological Monitoring and Abatement Program (BMAP) was developed to demonstrate that the effluent limitations established for the Oak Ridge Y-12 Plant protect the classified uses of the receiving stream (East Fork Poplar Creek), in particular, the growth and propagation of fish and aquatic life, as designated by the Tennessee Department of Health and Environment. A second purpose for the BMAP is to document the ecological effects resulting from implementation of a water pollution control program that will include construction of nine new wastewater treatment facilities over the next 4 years. ...
1989-10-01
Energy Technology Data Exchange (ETDEWEB)
The Argonne Boundary Layer Experiments (ABLE) facility, located in south central Kansas, east of Wichita, is devoted primarily to investigations of and within the planetary boundary layer (PBL), including the dynamics of the mixed layer during both day and night; effects of varying land use and land form; the interactive role of precipitation, runoff, and soil moisture; storm development; and energy budgets on scales of 10 to 100 km. Located entirely within the Walnut River watershed, ABLE provides intense measurements within the northeast quadrant (Fig. 1) of the Southern Great Plains (SGP) Cloud and Radiation Testbed (CART) of the Atmospheric Radiation Measurement (ARM) Program (Stokes and Schwarz, 1994). By combining the continuous measurements of ABLE with ancillary continuous measurements of, for example, the ARM and the Global Energy Water cycle Experiment (GEWEX) (Kinster and Shukla, 1990) programs, ABLE provides a ...
1998-06-05
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 maintenance training ...
1992-06-01
Waste Handeling Building Conceptual Study
Energy Technology Data Exchange (ETDEWEB)
The objective of the ''Waste Handling Building Conceptual Study'' is to develop proposed design requirements for the repository Waste Handling System in sufficient detail to allow the surface facility design to proceed to the License Application effort if the proposed requirements are approved by DOE. Proposed requirements were developed to further refine waste handling facility performance characteristics and design constraints with an emphasis on supporting modular construction, minimizing fuel inventory, and optimizing facility maintainability and dry handling operations. To meet this objective, this study attempts to provide an alternative design to the Site Recommendation design that is flexible, simple, reliable, and can be constructed in phases. The design concept will be input to the ''Modular Design/Construction and Operation Options Report'', ...
2000-11-06
RCRA Facilities Assessment (RFA)---Oak Ridge National Laboratory
Energy Technology Data Exchange (ETDEWEB)
US Department of Energy (DOE) facilities are required to be in full compliance with all federal and state regulations. In response to this requirement, the Oak Ridge National Laboratory (ORNL) has established a Remedial Action Program (RAP) to provide comprehensive management of areas where past and current research, development, and waste management activities have resulted in residual contamination of facilities or the environment. This report presents the RCRA Facility Assessment (RFA) required to meet the requirements of RCRA Section 3004(u). Included in the RFA are (1) a listing of all sites identified at ORNL that could be considered sources of releases or potential releases; (2) background information on each of these sites, including location, type, size, period of operation, current operational status, and information on observed or potential releases (as required in Section II.A.1 of the RCRA ...
1987-03-01
Design for environment for the National Ignition Facility
Energy Technology Data Exchange (ETDEWEB)
The National Ignition Facility (NIF) will be a U.S. Department of Energy (DOE) national center for inertial confinement fusion (ICF) and other research into the physics of high temperatures and high densities, and a vital element of the DOE`s nuclear weapons Stockpile Stewardship and Management Program. It will be used by scientists from a numerous different institutions and disciplines to support research advancements in national security, energy, basic science, and economic development. Multiple powerful laser beams will `ignite` small fusion targets, helping liberate more energy than is required to initiate the fusion reactions. This paper discusses the Design for Environment process for NIF, some of the subsequent activities resulting from the initial study, and a few of the lessons learned from this process. Subsequent activities include the development of a Pollution Prevention and Waste Minimization Plan (P2/WMin) for the ...
1998-05-01
CASCAD dry storage concept for spent fuel
International Nuclear Information System (INIS)
Further to a cost-benefit analysis of the various medium-term and long-term and H.L.W. storage possibilities, C.E.A. (French Atomic Energy Commission) and S.G.N. decided to develop an original dry storage process with natural convection cooling that offers many advantages: cut in the total investment and operating costs; high operating safety; natural convection cooling; existence of two containment barriers irrespective of the assumed clad conditions; flexible, modular and compact design. The process was first implemented in the so-called CASCAD Cadarache Facility (vault-type facility) constructed in Cadarache mainly to store fuel from Brennilis heavy water reactor. For the purpose, a large program was set up to develop and validate computer codes, in particular with the use of mockups. On the request of many clients, and owing to the outstanding operating results of the CASCAD Cadarache Facility, SGN ...
1994-08-01
An Experimental Study of Oil / Water Flow in Horizontal Pipes
Energy Technology Data Exchange (ETDEWEB)
The purpose of this thesis is to study the behaviour of the simultaneous flow of oil and water in horizontal pipes. In this connection, two test facilities are used. Both facilities have horizontal test sections with inner pipe diameters equal to 2 inches. The largest facility, called the model oil facility, has reservoirs of 1 m{sub 3} of each medium enabling flow rates as high as 30 m{sub 3}/h, which corresponds to mixture velocities as high as 3.35 m/s. The flow rates of oil and water can be varied individually producing different flow patterns according to variations in mixture velocity and input water cut. Two main classes of flows are seen, stratified and dispersed. In this facility, the main focus has been on stratified flows. Pressure drops and local phase fractions are measured for a large number of flow conditions. Among the instruments used are differential pressure ...
2001-07-01
Requirements and guidelines for NSLS experimental beam line vacuum systems: Revision A
Energy Technology Data Exchange (ETDEWEB)
Requirements are provided for NSLS beam line front ends and vacuum interlocks. Guidelines are provided for UHV beam line vacuum systems, including materials, vacuum hardware (pumps, valves, and flanges), acoustic delay lines and beam line fast valves, instrumentation, fabrication and testing, and the NSLS cleaning facility. Also discussed are the design review for experimenters' equipment that would be connected to the NSLS and acceptance tests for any beam line to be connected with the ring vacuum. Also appended are a description of the acoustic delay line as well as the NSLS vacuum standards and NSLS procedures. (LEW)
1986-10-01
Experimental research on X-ray spectrum emitted from hot laser-produced aluminium plasma
International Nuclear Information System (INIS)
The hot uniform aluminium plasma was produced by irradiating thin aluminium dotted foil smoothly with the 9th 0.53 ?m laser on Shenguang II laser facility. The emitted spectrum was measured from the front and tangential direction of the target with two crystal spectrometers, and the quantitative spectrum from the front of the target was obtained. The state of laser- produced plasma was simulated with the radiation hydrodynamics code MULTI-1D, and the emitted spectrum was calculated with the spectrum code of Collision-Radiation model under the simulated plasma state. The experimental spectrum accords with the simulated one. (authors)
2007-12-01
Analysis of enclosed sodium pool fire scenario in sodium fire experimental facility
International Nuclear Information System (INIS)
Liquid sodium is used as coolant in Fast Breeder Reactors (FBR). There is a likelyhood of sodium spillage in ambient air in the Steam Generator Building (SGB) of the FBR plant. Due to high chemical reactivity with oxygen, especially at temperatures greater than 573 K, it catches fire very easily. In order to carryout safety related experimental studies for different modes of sodium fires and to develop suitable mathematical models for the assessment of their consequences, an experimental facility (SFEF, Sodium Fire Experimental Facility) is being setup a IGCAR, Kalpakkam. The SFEF is having a 540 m"3 volume experimental hall. Stainless steel linear will be provided on the inside surfaces of experimental hall walls, ceiling and floor. Analysis has been carried out for enclosed sodium pool fire scenarios in SFEF by using sodium pool fire code ...
2007-04-22
National NIF Diagnostic Program Fiscal Year 2002 Second Quarter Report
Energy Technology Data Exchange (ETDEWEB)
Since October 2001 the development of the facility diagnostics for NIF has been funded by the NIF Director through the National NIF Diagnostic Program (NNDP). The current emphasis of the NNDP is on diagnostics for the early NIF quad scheduled to be available for experiment commissioning in FY03. During the past six months the NNDP has set in place processes for funding diagnostics, developing requirements for diagnostics, design reviews and monthly status reporting. Those processes are described in an interim management plan for diagnostics (''National NIF Diagnostic Program Interim Plan'', NIF-0081315, April 2002) and a draft Program Execution Plan (''Program Execution Plan for the National NlF Diagnostic Program'', NIF-0072083, October 2001) and documents cited therein. Work has been ...
2002-04-01
Computer modelling of eddy current probes
International Nuclear Information System (INIS)
Computer programs have been developed for modelling impedance and transmit-receive eddy current probes in two-dimensional axis-symmetric configurations. These programs, which are based on analytic equations, simulate bobbin probes in infinitely long tubes and surface probes on plates. They calculate probe signal due to uniform variations in conductor thickness, resistivity and permeability. These signals depend on probe design and frequency. A finite element numerical program has been procured to calculate magnetic permeability in non-linear ferromagnetic materials. Permeability values from these calculations can be incorporated into the above analytic programs to predict signals from eddy current probes with permanent magnets in ferromagnetic tubes. These programs were used to test various probe designs for new testing applications. Measurements of magnetic permeability in ...
1992-10-01
Clean Coal Program Research Activities
Although remarkable progress has been made in developing technologies for the clean and efficient utilization of coal, the biggest challenge in the utilization of coal is still the protection of the environment. Specifically, electric utilities face increasingly stringent restriction on the emissions of NO{sub x} and SO{sub x}, new mercury emission standards, and mounting pressure for the mitigation of CO{sub 2} emissions, an environmental challenge that is greater than any they have previously faced. The Utah Clean Coal Program addressed issues related to innovations for existing power plants including retrofit technologies for carbon capture and sequestration (CCS) or green field plants with CCS. The Program focused on the following areas: simulation, mercury control, oxycoal combustion, gasification, sequestration, chemical looping combustion, materials investigations and student research experiences. The goal of this ...
2009-03-31
Energy Technology Data Exchange (ETDEWEB)
A summary of the topics covered in papers presented at the 1995 Brookhaven joint conference on production, neutralization, and application of negative ion beams is given. The conference topics covered included plasma ion sources, plasma seeding of these sources for increased ion production, beam extraction and transport, computer simulation and design studies, and operation of existing and experimental ion source facilities. Application of the sources to accelerator, tokamak, and thin film deposition are discussed. (AIP) {copyright} {ital 1996 American Institute of Physics.}
1996-07-01
Information technology security at the Advanced Photon Source
International Nuclear Information System (INIS)
The proliferation of 'botnets,' phishing schemes, denial-of-service attacks, root kits, and other cyber attack schemes designed to capture a system or network creates a climate of concern for system administrators, especially for those managing accelerator and large experimental-physics facilities, as they are very public targets. This paper will describe the steps being taken at the Advanced Photon Source (APS) to protect the infrastructure of the overall network with emphasis on security for the APS control system.
2007-10-15
Energy Technology Data Exchange (ETDEWEB)
In this report, the descriptions of the DIVA test facility and those test matrixes are presented. The test sections simulate the downcomer annulus of DVI system with various scalling methodologies. The UPTF one has 1/7.5 scale and the APR-1400 test sections are reduced in 1/7 scale and 1/5 scale respectively. Also, the instrumentations, measuring methods are described. The major measuring parameters are ECC injection rate, air injection rate, bypass fraction, system pressure and so on. And finally, the operation procedure and experimental steps are introduced. From the DIVA tests, the multi-dimensional behaviors of two-phase flow in the downcomer during the reflood phase can be investigated using a transparent test facility. Also comparing the experimental data which are performed in various scale downcomer, it is expected that some criteria of scalling methodology proper to the DVI system can be ...
2002-03-01
Energy Technology Data Exchange (ETDEWEB)
High energy physics is a basic research domain with a well established European and international cooperation. Cooperation can be of different type depending on the size of the facilities involved (accelerators), on their financing, and on the type of experiments that use these facilities. The CERN, the European center for nuclear research, created in October 1954, is the best example of such a cooperation. This article examines first the juridical and scientifical structure of the CERN and the mode of organization of big experiments. Then, it presents the role of international committees in the establishment of a common scientific policy in Europe and in the rest of the world. Finally, the possible future evolution of the CERN towards a worldwide project is evoked. (J.S.)
2004-07-01
Reactor cover gas monitoring at the Fast Flux Test Facility
International Nuclear Information System (INIS)
The Fast Flux Test Facility (FFTF) is a 400-megawatt (thermal) sodium-cooled reactor designed for irradiation testing of fuels, materials and components for LMRs. It is operated by the Westinghouse Hanford Company for the US Department of Energy on the government-owned Hanford reservation near Richland, Washington. The first 100-day operating cycle began in April 1982 and the eighth operating cycle was completed in July 1986. Argon is used as the cover gas for all sodium systems at the plant. A program for cover gas monitoring has been in effect since the start of sodium fill in 1978. The argon is supplied to the FFTF by a liquid argon Dewar System and used without further purification.
1986-09-24
Energy Technology Data Exchange (ETDEWEB)
This Final Report documents the research accomplishments achieved in the first phase of operations of a new Advanced Photon Source beam line (7-ID MHATT-CAT) dedicated to real-time x-ray studies. The period covered by this report covers the establishment of a world-class facility for time-dependent x-ray studies of materials. During this period many new and innovative research programs were initiated at Sector 7 with support of this grant, most notably using a combination of ultrafast lasers and pulsed synchrotron radiation. This work initiated a new frontier of materials research: namely, the study of the dynamics of materials under extreme conditions of high intensity impulsive laser irradiation.
2003-09-10
Five years operating experience at the Fast Flux Test Facility
Energy Technology Data Exchange (ETDEWEB)
The Fast Flux Test Facility (FFTF) is a 400 Mw(t), loop-type, sodium-cooled, fast neutron reactor. It is operated by the Westinghouse Hanford Company for the United States Department of Energy at Richland, Washington. The FFTF is a multipurpose test reactor used to irradiate fuels and materials for programs such as Liquid Metal Reactor (LMR) research, fusion research, space power systems, isotope production and international research. FFTF is also used for testing concepts to be used in Advanced Reactors which will be designed to maximize passive safety features and not require complex shutdown systems to assure safe shutdown and heat removal. The FFTF also provides experience in the operation and maintenance of a reactor having prototypic components and systems typical of large LMR (LMFBR) power plants. The 5 year operational performance of the FFTF reactor is discussed in this report. 6 refs., 10 figs., 2 tabs.
1987-04-01
Five years operating experience at the Fast Flux Test Facility
International Nuclear Information System (INIS)
The Fast Flux Test Facility (FFTF) is a 400 Mw(t), loop-type, sodium-cooled, fast neutron reactor. It is operated by the Westinghouse Hanford Company for the United States Department of Energy at Richland, Washington. The FFTF is a multipurpose test reactor used to irradiate fuels and materials for programs such as Liquid Metal Reactor (LMR) research, fusion research, space power systems, isotope production and international research. FFTF is also used for testing concepts to be used in Advanced Reactors which will be designed to maximize passive safety features and not require complex shutdown systems to assure safe shutdown and heat removal. The FFTF also provides experience in the operation and maintenance of a reactor having prototypic components and systems typical of large LMR (LMFBR) power plants. The 5 year operational performance of the FFTF reactor is discussed in this report. 6 refs., 10 figs., 2 tabs.
1987-09-13
Annual report of JMTR, 1994. April 1, 1994 - March 31, 1995
Energy Technology Data Exchange (ETDEWEB)
In FY1994, JMTR was in operation during 4 operation cycles with low enriched Uranium(LEU,20%) fuel for irradiation study of nuclear fuels and materials and for radioisotope production. Irradiation studies were carried out using capsules, Oarai Gas Loop-1(OGL-1), Oarai Shroud Facility(OSF-1) and hydraulic rabbits irradiation facilities in support of LWR, FBR, HTTR and thermonuclear reactor. Irradiation studies on blanket materials were intensively carried out. Power ramping tests were carried out and the future program is under consideration. For R and D works, neutron spectrum evaluation technology, re-instrumentation technique for irradiation fuel rod, remote controlled SEM apparatus and examination technique with miniaturized specimens were successfully developed. (author).
1996-03-01
Increasing pipe-cable section lengths. Final report
Energy Technology Data Exchange (ETDEWEB)
This report summarizes the results of an experimental program which developed a needed reliable data base on modern pipe-type cable construction from which designers can knowledgeably consider maximizing cable pulling lengths with resulting cost savings. The program comprised evaluations of available commercial constructions over the range of conductor sizes (both copper and aluminum) and insulation thicknesses in general utilization. The work focussed on determining the cable's performance under the three mechanical stress modes to which the cable is subjected during installation; (a) tension and elongation, (b) torsion and (c) sidewall (bearing) pressure in bends. Additionally, the program included experimentation to determine the effective coefficient of friction of the various combinations of modern skid wire materials and pipe filling oils used as lubricants with the ...
1983-03-01
Using long term biological monitoring data to evaluate the recovery of disturbed systems
International Nuclear Information System (INIS)
Biological monitoring has been conducted in industrially impacted streams near US Department of Energy facilities in Tennessee and Kentucky for almost ten years. A comprehensive Biological Monitoring and Abatement Program, which was developed to meet National Pollutant Discharge Elimination System permit requirements, includes tasks on (1 ) toxicity testing; (2) bioaccumulation in aquatic and terrestrial biota; (3) bioindicators of fish health; and (4) fish, macroinvertebrate, and periphyton community surveys. These studies have been used successfully to characterize spatial trends and demonstrate temporal recovery resulting from remedial actions and pollution abatement activities, identify contaminant sources, and provide data for conducting ecological risk assessments. The program uses multiple lines of evidence to evaluate stream recovery and illustrates the importance of using an integrated approach when determining ...
1995-11-05
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 interested in the waste-management program in the formulation of the basic principles on ...
1991-09-01
Multiple Computer-Automated Structure Evaluation program study of aquatic toxicity 1: Guppy
Energy Technology Data Exchange (ETDEWEB)
An acute fish toxicity model was constructed on the basis of a wide series of experimental data for guppy. The Multiple Computer-Automated structure Evaluation program was used to construct the model. The created model possesses very good predictive ability. It can correctly predict acute toxicity for guppy for 80% of compounds with an average error of only 0.63 log unit per median lethal concentration. The importance of the narcosis effect was demonstrated. The main toxicophores, corresponding to polar narcosis and to the reactive chemicals, were identified.
1999-11-01
Fundamental R and D program on water chemistry of supercritical pressure water under radiation field
International Nuclear Information System (INIS)
In a supercritical water-cooled reactor, property of water changes significantly around the critical point. It is expected that irradiation and change of water property will affect the chemistry and material corrosion. Deep understanding of interactions between supercritical water and materials under irradiation is important. However, comprehensive data on radiolysis, kinetics, corrosion and thermodynamics have not been obtained due to the severe experimental condition. To get such data by experiments and computer simulations, a national program funded by Ministry of Education, Culture, Sports, Science and Technology (MEXT) has been started since December 2002. (author)
2003-09-15
UNITED STATES DEPARTMENT OF ENERGY WASTE PROCESSING ANNUAL TECHNOLOGY DEVELOPMENT REPORT 2007
Energy Technology Data Exchange (ETDEWEB)
The Office of Environmental Management's (EM) Roadmap, U.S. Department of Energy--Office of Environmental Management Engineering & Technology Roadmap (Roadmap), defines the Department's intent to reduce the technical risk and uncertainty in its cleanup programs. The unique nature of many of the remaining facilities will require a strong and responsive engineering and technology program to improve worker and public safety, and reduce costs and environmental impacts while completing the cleanup program. The technical risks and uncertainties associated with cleanup program were identified through: (1) project risk assessments, (2) programmatic external technical reviews and technology readiness assessments, and (3) direct site input. In order to address these needs, the technical risks and uncertainties were compiled and divided into the ...
2008-08-12
Experimental Investigation and RELAP5 Modeling of Two-Phase Flow in Horizontal Rectangular Channel
British Library Electronic Table of Contents (United Kingdom)
The investigation of steam, water, and air flow characteristics in horizontal channel is a part of major investigations program at the Lithuanian Energy Institute. The objective of this program is to identify condensation effects on two-phase flow stability and to predict conditions when rapid condensation could be induced in two-phase condensable flow. This article presents investigation of steam-water and air multiphase flow in nearly horizontal rectangular channel. The experimental data for pressure drop and interfacial and wall shear stresses in the channel with uniform distribution of void fraction are presented in this paper. Overall channel dimensions are length = 1.2 m, width = 0.02 m, height = 0.1 m; however, the test section was about 0.84 m in length. Three different flow types ...
2011-01-01
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 ...
1994-01-01
Waste characterization study for the Kemp's Ridley sea turtle. Technical memo
Energy Technology Data Exchange (ETDEWEB)
The Kemp's Ridley sea turtle, Lepidochelys kempi, is an endangered species. The National Marine Fisheries Service's Head Start program is part of an international operation to save the turtles from extinction. Under the Head Start program, eggs from the Ridley's only known wild nesting beach at Rancho Nuevo in Mexico are transported to Padre Island on the Texas coast to be hatched. The head start enables the turtles to develop a survival advantage. The principal objective was to develop baseline waste-characterization data required to design a waste-water treatment scheme for the Galveston Head Start facility. As a secondary objective, preliminary testing of some filtration components was undertaken to determine which units were most appropriate for inclusion in a wastewater treatment scheme.
1988-02-01
The Computation Directorate at Lawrence Livermore National Laboratory
Energy Technology Data Exchange (ETDEWEB)
The Computation Directorate at Lawrence Livermore National Laboratory has four major areas of work: (1) Programmatic Support -- Programs are areas which receive funding to develop solutions to problems or advance basic science in their areas (Stockpile Stewardship, Homeland Security, the Human Genome project). Computer scientists are 'matrixed' to these programs to provide computer science support. (2) Livermore Computer Center (LCC) -- Development, support and advanced planning for the large, massively parallel computers, networks and storage facilities used throughout the laboratory. (3) Research -- Computer scientists research advanced solutions for programmatic work and for external contracts and research new HPC hardware solutions. (4) Infrastructure -- Support for thousands of desktop computers and numerous LANs, labwide unclassified networks, computer security, computer-use policy.
2006-09-07
Production of radioisotopes in the ORNL 86-inch cyclotron
Energy Technology Data Exchange (ETDEWEB)
The radioisotope production facilities and programs of the 86-Inch Cyclotron are reviewed in this presentation. The 86-Inch Cyclotron is designed to accelerate protons to a maximum energy of 22 MeV for internal targets. These protons are used to bombard metals that are electroplated, potted or soldered to water-cooled plates. Additionally, metals and inorganic compounds are bombarded in water-cooled tube targets. High radioisotope production rates are obtained by beam currents as large as 3 mA. Production rates for /sup 11/C, /sup 57/Co, /sup 67/Ga, /sup 68/Ge, /sup 109/Cd, and other isotopes are presented. The production of /sup 11/C for the carboxyl labeling of amino acids in cooperation with Oak Ridge Associated Universities is discussed. The 86-Inch Cyclotron is used for those programs requiring a larger beam current than is available from commercial cyclotrons.
1981-04-01
Household batteries: Evaluation of collection methods
Energy Technology Data Exchange (ETDEWEB)
While it is difficult to prove that a specific material is causing contamination in a landfill, tests have been conducted at waste-to-energy facilities that indicate that household batteries contribute significant amounts of heavy metals to both air emissions and ash residue. Hennepin County, MN, used a dual approach for developing and implementing a special household battery collection. Alternative collection methods were examined; test collections were conducted. The second phase examined operating and disposal policy issues. This report describes the results of the grant project, moving from a broad examination of the construction and content of batteries, to a description of the pilot collection programs, and ending with a discussion of variables affecting the cost and operation of a comprehensive battery collection program. Three out-of-state companies (PA, NY) were found that accept spent batteries; difficulties in ...
1992-01-01
Household batteries: Evaluation of collection methods
Energy Technology Data Exchange (ETDEWEB)
While it is difficult to prove that a specific material is causing contamination in a landfill, tests have been conducted at waste-to-energy facilities that indicate that household batteries contribute significant amounts of heavy metals to both air emissions and ash residue. Hennepin County, MN, used a dual approach for developing and implementing a special household battery collection. Alternative collection methods were examined; test collections were conducted. The second phase examined operating and disposal policy issues. This report describes the results of the grant project, moving from a broad examination of the construction and content of batteries, to a description of the pilot collection programs, and ending with a discussion of variables affecting the cost and operation of a comprehensive battery collection program. Three out-of-state companies (PA, NY) were found that accept spent batteries; difficulties in ...
1992-12-31
Assessment and control of fetal exposure
Energy Technology Data Exchange (ETDEWEB)
The assessment and control of fetal exposure to radiation in the workplace is an issue that is complicated by both biological and political/social ramifications. As a result of the dramatic increase in the number of women employed as radiation workers during the past 10 years, many facilities using radioactive materials have instituted fetal protection programs with special requirements for female radiation workers. It is necessary, however, to ensure that any fetal protection program be developed in such a way as to be nondiscriminatory. A study has been initiated whose purpose is to balance the political/social and the biological ramifications associated with occupational protection of the developing embryo/fetus. Several considerations are involved in properly balancing these factors. These considerations include appropriate methods of declaring the pregnancy, training workers, controlling the dose to the embryo/fetus, ...
1991-10-01
An intelligent design methodology for nuclear power systems
Energy Technology Data Exchange (ETDEWEB)
The goal of this investigation is to research possible methodologies into automating the design of, specifically, nuclear power facilities; however, it is relevant to all thermal power systems. The strategy of this research has been to concentrate on individual areas of the thermal design process, investigate procedures performed, develop methodology to emulate that behavior, and prototype it in the form of a computer program. The design process has been generalized as follows: problem definition, design definition, component selection procedure, optimization and engineering analysis, testing and final design with the problem definition defining constraints that will be applied to the selection procedure as well as design definition. The result of this research is a prototype computer program applying an original procedure for the selection of the best set of real components that would be used in constructing a system with ...
1989-01-01
Phase chemistry and radionuclide retention of high level radioactive waste tank sludges
Energy Technology Data Exchange (ETDEWEB)
The US Department of Energy (DOE) has millions of gallons of high level nuclear waste stored in underground tanks at Hanford, Washington and Savannah River, South Carolina. These tanks will eventually be emptied and decommissioned. This will leave a residue of sludge adhering to the interior tank surfaces that may contaminate groundwaters with radionuclides and RCRA metals. Experimentation on such sludges is both dangerous and prohibitively expensive so there is a great advantage to developing artificial sludges. The US DOE Environmental Management Science Program (EMSP) has funded a program to investigate the feasibility of developing such materials. The following text reports on the success of this program, and suggests that much of the radioisotope inventory left in a tank will not move out into the surrounding environment. Ultimately, such studies may play a significant role in developing safe and ...
2000-05-19
Tiger Team assessment of the Brookhaven National Laboratory
Energy Technology Data Exchange (ETDEWEB)
This report documents the results of the Department of Energy's (DOE's) Tiger Team Assessment conducted at Brookhaven National Laboratory (BNL) in Upton, New York, between March 26 and April 27, 1990. The BNL is a multiprogram laboratory operated by the Associated Universities, Inc., (AUI) for DOE. The purpose of the assessment was to provide the status of environment, safety, and health (ES H) programs at the laboratory. The scope of the assessment included a review of management systems and operating procedures and records; observations of facility operations; and interviews at the facilities. Subteams in four areas performed the review: ES H, Occupational Safety and Health, and Management and Organization. The assessment was comprehensive, covering all areas of ES H activities and waste management operations. Compliance with applicable Federal, State, and local regulations; applicable DOE Orders; and ...
1990-06-01
Energy Technology Data Exchange (ETDEWEB)
This Progress Report describes the operation of the Los Alamos Meson Physics Facility (LAMPF) and the research programs carried out there for the years 1992 and 1993. The accelerator operated for over 100 days in 1992, providing beams of H{sup +}, H{sup {minus}}, and polarized H{sup {minus}} for a rich and varied research program in nuclear physics. The accelerator had only fair beam availability in 1992 (for example, the average H{sup +} beam availability was 72%), caused largely by problems in the 201-MHz rf system. A major effort was expended to address these problems before the 1993 run. These efforts were rewarded by good beam availability in 1993 and few problems with the 201-MHz system. LAMPF operated remarkably smoothly during 1993, in the midst of a period of great uncertainty in the future of the facility and the downsizing of MP Division, which led to the loss of a large number of key people ...
1994-07-25
Maintenance implementation plan for the Plutonium Finishing Plant. Revision 3
Energy Technology Data Exchange (ETDEWEB)
This document outlines the Maintenance Implementation Plan (MIP) for the Plutonium Finishing Plant (PFP) located at the Hanford site at Richland, Washington. This MIP describes the PFP maintenance program relative to DOE order 4330.4B. The MIP defines the key actions needed to meet the guidelines of the Order to produce a cost-effective and efficient maintenance program. A previous report identified the presence of significant quantities of Pu-bearing materials within PFP that pose risks to workers. PFP`s current mission is to develop, install and operate processes which will mitigate these risks. The PFP Maintenance strategy is to equip the facility with systems and equipment able to sustain scheduled PFP operations. The current operating run is scheduled to last seven years. Activities following the stabilization operation will involve an Environmental Impact Statement (EIS) to determine future plant activities. This ...
1996-03-01
Heavy water reactor facility large-scale containment cooling test program
The Heavy Water Reactor Facility (HWRF), as part of the defense-in-depth philosophy to mitigate the effect of design-basis and severe accidents, is equipped with a passive containment cooling system (PCCS). The function of the PCCS is to provide a safety-grade path to the ultimate heat sink for the removal of the reactor coolant system sensible heat and core decay heat. Ambient air enters an annular space between the steel containment shell and the surrounding concrete shield building through inlets in the shield building wall, is heated via natural convection, rises, and exits the building through a chimney located above the containment dome. A test program is in place to access parameters important to the effective operation of the PCCS. This paper focuses on the large-scale tests (LSTs). The objectives of these tests are as follows: (1) demonstrate natural circulation cooling with more prototypic cylinder and dome surface area ratios than ...
1992-01-01
Heavy water reactor facility large-scale containment cooling test program
International Nuclear Information System (INIS)
The Heavy Water Reactor Facility (HWRF), as part of the defense-in-depth philosophy to mitigate the effect of design-basis and severe accidents, is equipped with a passive containment cooling system (PCCS). The function of the PCCS is to provide a safety-grade path to the ultimate heat sink for the removal of the reactor coolant system sensible heat and core decay heat. Ambient air enters an annular space between the steel containment shell and the surrounding concrete shield building through inlets in the shield building wall, is heated via natural convection, rises, and exits the building through a chimney located above the containment dome. A test program is in place to access parameters important to the effective operation of the PCCS. This paper focuses on the large-scale tests (LSTs). The objectives of these tests are as follows: (1) demonstrate natural circulation cooling with more prototypic cylinder and dome surface area ratios than ...
1992-11-15
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 ...
1997-04-01
Progress and Plans for R&D and the Conceptual Design of the ILC Main Linacs
The International Linear Collider Main Linacs are based on superconducting accelerator structures operating at 1.3 GHz. The basis for this design has been developed and tested at DESY and R&D is progressing at many laboratories around the world including DESY, Orsay, KEK, FNAL, SLAC, Cornell, and JLAB. The status of the TESLA-style cavities and rf system will be reviewed and parameters for the ILC linac will be described. The role of the different linac test facilities will discussed and the critical items and R&D program to support a Conceptual Design and Technical Design will be outlined.
2005-01-01
Divison of Environmental Education and Development Fiscal Year 1992 annual report
Energy Technology Data Exchange (ETDEWEB)
Primary design criterion for this division`s education activities is directly related to meeting the goal of environmental compliance on an accelerated basis and cleanup of the 1989 inventory of inactive sites and facilities by the year 2019. Therefore, the division`s efforts are directed toward stimulating knowledge and capability to achieve the goals while contributing to DOE`s overall goal of increasing scientific, mathematical, and technical literacy and competency. This annual report is divided into: overview, workforce development, academic partnerships, scholarships/fellowships, environmental restoration and waste management employment program, community colleges, outreach, evaluation, and principal DOE contacts.
1992-12-31
CLEO: a knowledge-based refueling assistant at FFTF
International Nuclear Information System (INIS)
A computer software system, CLEO, is used to assist in the planning and performance of the reactor refueling operations at the Fast Flux Test Facility (FFTF). It is a recently developed application of artificial intelligence software with both expert systems and automated reasoning aspects. CLEO, an acronym for Cloned LEO, is a logic-based computer program written in Pascal. It imitates the processes that the refueling expert for FFTF performs in organizing the refueling of FFTF. The computer assistant seeks to organize the sequence of core component movements according to the rules and logic used by the expert. In this form, CLEO has aspects that tie it to both the expert systems and automated reasoning areas within the artificial intelligence field.
1985-11-10
Registration of Hanford Site Class V underground injection wells
Energy Technology Data Exchange (ETDEWEB)
This document was requested by the Washington State Department of Ecology. Based on the State Underground Injection Control Program, as described in the Washington Administrative Code, French drains and reverse wells are being registered as Class V wells. Information on out-of-service French drains, out-of-service reverse wells, and out-of-service cribs that are deeper than their largest surface dimension is also provided. The data for this submittal were taken from the Waste Information Database System (WIDS) and the Hanford Environmental Compliance Record (HECR) database. The current definition used in WIDS for an ''inactive facility'' is one that either no longer receives waste or plans to in the future. The facilities listed in WIDS as inactive have all been listed as ''out-of-service.'' Information concerning the deactivation method for a ...
1988-05-01
Energy Technology Data Exchange (ETDEWEB)
This report presents the results of the preliminary assessment (PA) conducted by Argonne National Laboratory at the Georgia Army National Guard (GAARNG) facility near Hinesville, Georgia, known as the National Guard Training Center (NGTC). Preliminary assessments of federal facilities are being conducted to compile the information necessary for completing preremedial activities and to provide a priority basis for completing corrective actions (where necessary) in response to releases of hazardous substances. The principal objective of the PA is to characterize the site accurately and determine the need for further action by examining previous site activities, types and quantities of hazardous substances utilized, and potential pathways by which contamination could affect public health and the environment. The scope of this assessment is limited to the facilities and past activities contained within the NGTC. Preliminary ...
1993-07-01
Energy Technology Data Exchange (ETDEWEB)
It is desired that the data on past ground information are easily picked out and used effectively when construction of power facilities such as power plants is planned. For this purpose, a data base system that is available for survey planning and design business has been developed. This system is divided into subsystems for input, registration, and output, which all can be processed by the personal computers. It also has a retrieval function for maps such as area maps and power facility maps in addition to a retrieval function for characters. As output functions, the system has a function to extract ground information through maps of facilities and their peripheries, an output function for geological profiles and soil test results, and liquefaction analysis and design constant setting support functions. As instances, applications of this system to the thermal power plant location program and to the ...
1994-09-05
The NIST/NRL free-electron laser facility
International Nuclear Information System (INIS)
A free-electron laser (FEL) user facility is discussed. The FEL, which will be operated as an oscillator, will be driven by the electron beam of the racetrack microtron (RTM) that is nearing completion. Variation of the electron kinetic energy from 17 MeV to 185 MeV will permit the FEL wavelength to be tuned from 200 nm to 10 #mu#m. Performance will be enhanced by the high brightness, low energy spread, and continuous pulse nature of the RTM electron beam. The authors are designing a new injector to increase the peak current of the RTM. A 3.6-m undulator is under construction, and the 9-m optical cavity is under design. The FEL will emit a continuous train of 3-ps pulses at 66 MHz with an average power of 10--200 W, depending on the wavelength, and a peak power of up to several hundred kW. An experimental area is being prepared with up to five stations for research using the FEL beam.
1989-04-24
Energy Technology Data Exchange (ETDEWEB)
For the application of dynamic neutron radiography to the two-phase flow research using HANARO, several experimental items to which the radiography technique is beneficial were identified through the review of the outputs from the related researches and the discussions with experts. Also, the investigation of the equipments including the beam port, camera and converter was made and a hardware and a software for image processing were equipped. It was confirmed that the calibration curve for the attenuation of neutron beam in fluid which is required for the two-phase flow experiment could be obtained by the computer code calculation. Based on the investigation results on the equipment and the results from the measurement of BNCT beam characteristics, a high speed camera and an image intensifier will be purchased. Then, the high speed dynamic neutron radiography facility for two-phase flow experiments will be fully equipped.
2001-01-01
Energy Technology Data Exchange (ETDEWEB)
Since 1999, several studies on nuclear fuels were realised in C11/C12 Atalante Hot Cell. This paper presents firstly an overview of the apparatus used for fuel dissolution and characterisation like reactor design, gas trapping flask and solid/liquid separation. Then, the general methodology is described as a function of fuel, temperature, reagents, showing for each step, the reachable experimental data: Dissolution rate, chemical and radiochemical fuel composition including volatile LLRN, insoluble mass, composition, morphology, cladding chemical, radiochemical and physical characterisation using SIMS (made in Cadarache/LECA facilities), MEB. To conclude, some of the obtained results on 129I and 14C composition of oxide fuels, rate of dissolution and first results on dissolution studies of RERTR UMo fuel will be detailed. (Author)
2005-01-01
Modeling, Simulation Design and Control of Hybrid-Electric Vehicle Drives
Energy Technology Data Exchange (ETDEWEB)
Ohio State University (OSU) is uniquely poised to establish such a center, with interdisciplinary emphasis on modeling, simulation, design and control of hybrid-electric drives for a number of reasons, some of which are: (1) The OSU Center for Automotive Research (CAR) already provides an infrastructure for interdisciplinary automotive research and graduate education; the facilities available at OSU-CAR in the area of vehicle and powertrain research are among the best in the country. CAR facilities include 31,000 sq. feet of space, multiple chassis and engine dynamometers, an anechoic chamber, and a high bay area. (2) OSU has in excess of 10 graduate level courses related to automotive systems. A graduate level sequence has already been initiated with GM. In addition, an Automotive Systems Engineering (ASE) program cosponsored by the mechanical and electrical engineering programs, had been formulated ...
2005-09-30
Energy Technology Data Exchange (ETDEWEB)
This document is the third annual revision of the plans and schedules for implementing the Federal Facility Agreement (FFA) compliance program, originally submitted in 1992 as ES/ER-17&D1, Federal Facility Agreement Plans and Schedules for Liquid Low-Level Radioactive Waste Tank Systems at Oak Ridge National Laboratory, Oak Ridge, Tennessee. This document summarizes the progress that has been made to date in implementing the plans and schedules for meeting the FFA commitments for the Liquid Low-Level Waste (LLLW) System at Oak Ridge National Laboratory (ORNL). Information presented in this document provides a comprehensive summary to facilitate understanding of the FFA compliance program for LLLW tank systems and to present plans and schedules associated with remediation, through the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) process, of LLLW tank systems that ...
1995-06-01
From tankers to tissues : tracking the degradation and fate of oil discharges in Port Valdez, Alaska
Energy Technology Data Exchange (ETDEWEB)
An average of 9 million gallons per day of oil-contaminated ballast water off loaded from tankers are treated at the Alyeska Pipeline Service Company Ballast Water Treatment Facility at the terminus of the Trans-Alaska Pipeline in Port Valdez, Alaska. This paper focuses on the results of 2 Prince William Sound Regional Citizens' Advisory Council monitoring programs which detail changes in the chemical composition of treated ballast water as it moves from tankers through the facility and subsequently traces the effluent hydrocarbons into the receiving environment of Port Valdez. The treatment facility involves gravity separation tanks, dissolved air flotation cells and biological treatment tanks. Effluent containing traces of volatile aromatics, including benzene, toluene, ethylbenzene and xylenes, low levels of oil, saturated hydrocarbons and polycyclic aromatic hydrocarbons is being ...
2005-07-01
Large sample NAA facility at GRR-1 research reactor: Design and applications
International Nuclear Information System (INIS)
Full text: A Large Sample Neutron Activation Analysis (LSNAA) facility is under development at GRR-1 research reactor, NCSR 'Demokritos'. The LSNAA facility design incorporates sample irradiation in the reactor's graphite thermal neutron column and subsequent measurement of the activity induced at a gamma spectroscopy system with gamma ray transmission measurement options included. Monte Carlo neutron and photon transport code MCNP-4C was used to model the facility. Appropriate correction factors accounting for neutron field perturbation during sample irradiation, high purity germanium detector efficiency for the volume source and gamma ray self-absorption within the sample itself were derived. The results of the computations were experimentally verified by activation foil measurements for a set of known materials and a range of sample sizes extending up to 10 litters. Moreover, the special issue of ...
2003-06-09
Optimization techniques for parameter estimations: case studies in CO{sub 2} separation processes
Energy Technology Data Exchange (ETDEWEB)
Application of an optimization technique to extract the non-ideal parameters of gas absorption with chemical reactions process was described. The gas absorption was modeled using mass transfer theory to represent the realistic behaviors of an absorber. The model was a highly non-linear iterative model which correlated the overall rate of absorption as the function of unknown non-ideal parameters, including the physical liquid mass transfer coefficient and the wetted interfacial area of of packings. The optimization program was developed to minimize the sum of squares of relative errors between the model predictions and the experimental data. Four sets of experimental data (case studies) with different operating conditions were used for extracting parameters. Comparisons between predicted and experimental measured overall absorption rate were in good agreement, average absolute value of relative errors ...
1995-12-31
We present in this article a detailed quantitative discussion of the measurement of the leptonic mixing angle theta_13 through currently scheduled reactor neutrino oscillation experiments. We thus focus on Double Chooz (Phase I & II), Daya Bay (Phase I & II) and RENO experiments. We perform a unified analysis, including systematics, backgrounds and accurate experimental setup in each case. Each identified systematic error and background impact has been assessed on experimental setups following published data when available and extrapolating from Double Chooz acquired knowledge otherwise. After reviewing the experiments, we present a new analysis of their sensitivities to sin^2(2 theta_13) and study the impact of the different systematics based on the pulls approach. Through this generic statistical analysis we discuss the advantages and drawbacks of each experimental setup.
2007-01-01
Efficient and economical utilization of wind power will require the ability to measure and ultimately predict the effects fluctuations in the incident wind will have on a wind turbine. In order to quantitatively assesss these effects, experimental techniques have been developed which allow analysis of full-scale performance of wind turbines with particular emphasis on the effects caused by turbulence in the incident wind. Examples of these techniques are presented using data from the DOE/Sandia Vertical Axis Wind Turbine (VAWT) program.
1981-01-01
Steam generator design improvements for the candu wolsung nuclear power plant
International Nuclear Information System (INIS)
Design considerations are given for the secondary side region of a vertical U-tube nuclear stream generator with an integral preheater. The thermal shield design, the novel recirculating water flow distribution scheme, the high porosity tube supports used in the parallel flow regions, and the U-bend supports are discussed for the Wolsung Plant steam generators. Experimental and analytical development programs undertaken to verify the design features are outlined.
1978-01-01
Software for Data Analysis Programming with R
Although statistical design is one of the oldest branches of statistics, its importance is ever increasing, especially in the face of the data flood that often faces statisticians. It is important to recognize the appropriate design, and to understand how to effectively implement it, being aware that the default settings from a computer package can easily provide an incorrect analysis. The goal of this book is to describe the principles that drive good design, paying attention to both the theoretical background and the problems arising from real experimental situations. Designs are motivated t
2008-01-01
Research in experimental elementary particle physics. A proposal to the U.S. Department of Energy
Energy Technology Data Exchange (ETDEWEB)
We report on the activities of the High Energy Physics Group at the University of Texas at Arlington for the period 1994-95. We propose the continuation of the research program for 1996-98 with strong participation in the detector upgrade and physics analysis work for the D0 Experiment at Fermilab, prototyping and pre-production studies for the muon and calorimeter systems for the ATLAS Experiment at CERN, and detector development and simulation studies for the PP2PP Experiment at Brookhaven.
1995-04-13
Process in Plasma Research at IPJ and IPPLM, POLAND
International Nuclear Information System (INIS)
The most important results of theoretical and experimental studies of plasmas, which have been achieved at the IPJ in Swierk and IPPLM in Warsaw recently, are presented. Studies of physical phenomena in PF discharges, development of diagnostic techniques and research on new plasma technologies, as performed at IPJ, have been summarized. Studies of dense magnetized plasmas, investigation of physics and applications of laser-produced plasmas; and research on the development of advanced diagnostic techniques for the EUROATOM fusion program, as performed at IPPLM, are also described.
2006-01-01
PFB coal fired combined cycle development program. Final report
Energy Technology Data Exchange (ETDEWEB)
A final report is presented on the design, environmental characteristics, performance and maintainability, and economic analysis of a commercial 663 MWe coal-fired combined cycle power plant using pressurized fluidized bed combustion, and advanced technology in the hot gas cleanup system and gas turbines. Experimental data on the performance of each of the major components are included. (LCL)
1981-03-01
Forschungszentrum Juelich, Institut fuer Kernphysik. Annual report 1994
Energy Technology Data Exchange (ETDEWEB)
This volume contains the annual report describing the work carried out at COSY (Cooled Synchrotron Storage Ring at KFA Juelich). The results in both machine and physics program are presented on the main topics experimental nuclear physics, theoretical nuclear physics, accelerator developments and technical developments. (MSA)
1995-02-01
Data analysis software for researching transportation of radiopharmaceuticals in body
International Nuclear Information System (INIS)
In research of nuclear medicine and development of radiopharmaceuticals, it is necessary to do data analysis and know transportation behaviors of the radionuclide in tissues or organs concerned. Based on polynomial fitting method, we developed the software INDFIT 1.0 programmed by Microsoft Visual Basic 6.0 (VB 6) for the data analysis. Experimental calculations showed that the software was of practical use
2003-05-01
Comparison of SAND-II and FERRET
A comparison was made of the advantages and disadvantages of two codes, SAND-II and FERRET, for determining the neutron flux spectrum and uncertainty from experimental dosimeter measurements as anticipated in the FFTF Reactor Characterization Program. This comparison involved an examination of the methodology and the operational performance of each code. The merits of each code were identified with respect to theoretical basis, directness of method, solution uniqueness, subjective influences, and sensitivity to various input parameters.
Analysis of a manipulator in relation to collision between a link and an object
British Library Electronic Table of Contents (United Kingdom)
In this article, equations of motion of a manipulator are derived after consideration of the characteristics of the driving source. By considering a collision between a link and an object, and considering the active motion to absorb the kinetic energy of the object, the trajectories for saving energy are calculated by the iterative dynamic programming (IDP) method. The dynamic characteristics of manipulator control based on the trajectory for saving energy are also analyzed theoretically and investigated experimentally.
2011-01-01
International Nuclear Information System (INIS)
Full text: The ITWG was first formed in 1995 for the purpose of fostering international cooperation for combating illicit trafficking of nuclear materials. The initial focus for the ITWG was on the development of nuclear forensics to help answer attribution questions regarding nuclear materials of unknown origin. More recently, the ITWG has also expanded its focus to include detection of nuclear materials during transit. This paper presents some of the key developments by this group and their potential impact for combating nuclear smuggling. The initial focus of the ITWG was to write a status report on international cooperation on nuclear smuggling forensic analysis. This 26-page report summarized previous work on nuclear forensics and gave an initial analysis on prioritizing techniques and methods for forensic analysis regarding source and route attribution. This report was submitted to the G-8 countries, and shortly thereafter, nuclear forensics was endorsed at the Moscow Summit in ...
2002-10-21
International Nuclear Information System (INIS)
The Melt Vessel Interaction (MVI) project is concerned with the consequences of the interactions that a core melt, generated during a postulated severe accident in a light water reactor, may have with the pressure vessel. In particular, the issues concerned with the failure of the vessel bottom head are the focus of the research. The specific objectives of the project are to obtain data and develop validated models, which could be applied to prototypic plants, and accident conditions, for resolution of issues related to the melt vessel interactions. The project work has been performed by nine partners having varied responsibility. The work included a large number of experiments, with simulant materials, whose observations and results are employed, respectively, to understand the physical mechanisms and to develop validated models. Applications to the prototypic geometry and conditions have also been performed. This report is volume 1 of the Final Report for the Project, in which a ...
1995-10-01
Chemical-equilibrium calculations for aqueous geothermal brines
Energy Technology Data Exchange (ETDEWEB)
Results from four chemical-equilibrium computer programs, REDEQL.EPAK, GEOCHEM, WATEQF, and SENECA2, have been compared with experimental solubility data for some simple systems of interest with geothermal brines. Seven test cases involving solubilities of CaCO/sub 3/, amorphous SiO/sub 2/, CaSO/sub 4/, and BaSO/sub 4/ at various temperatures from 25 to 300/sup 0/C and in NaCl or HCl solutions of 0 to 4 molal have been examined. Significant differences between calculated results and experimental data occurred in some cases. These differences were traced to inaccuracies in free-energy or equilibrium-constant data and in activity coefficients used by the programs. Although currently available chemical-equilibrium programs can give reasonable results for these calculations, considerable care must be taken in the selection of free-energy data and methods of calculating activity ...
1981-05-01
Integrating the Integrators - A Roadmap to Success
Energy Technology Data Exchange (ETDEWEB)
The U.S. Department of Energy Environmental Management's (DOE-EM) investments in science and technology, as well as science and technology investments associated with other parts of the DOE are aimed at meeting the Departments cleanup goals. These investments, primarily focused on EM's cleanup mission, comprise the Environmental Quality Research and Development (R&D) portfolios. Synchronizing EM's Cleanup Project Managers (operations facility and process owners throughout the DOE complex) operational needs with EM R&D including the extensive work of the six Focus Areas (major thrust areas within DOE-EM) has been a continuing challenge. This recent initiative to better integrate the R&D program is in response to evolving needs within the Department to apply proven system engineering methods to clarify requirements and define EM's process to effectively orchestrate their R&D ...
1999-03-01
Instrumentation and Controls Division progress report, September 1, 1980-July 1, 1982
Energy Technology Data Exchange (ETDEWEB)
Activities are reported by the Reactor Systems Section, Research Instrument Section, and the Measurement and Controls Engineering Section. Reactor system activities include dynamic analysis, survillanc and diagnostic methods, design and evaluation, detectors, facilities support, process instrumentation development, and special assignments. Activities in the Research Instrument Section include the Navy-ORNL RADIAC development program, advanced ..gamma.. and x ray detector systems, neutron detection and subcriticality measurements, circuit development, position-sensitive detectors, stand-alone computers, environmental monitoring-detectors and systems, plant security, engineering support for fusion energy division, engineering support for accelerator physics, and communications: radio, closed-circuit tv, and computer. Activities in the Measurement and Controls Engineering Section include the AVLIS program; gas centrifuge ...
1982-12-01
ICPP water inventory study project summary report
Energy Technology Data Exchange (ETDEWEB)
The Idaho Chemical Processing Plant (ICPP) Water inventory Study was initiated in September 1993 with the formation of a joint working group consisting of representatives from DOE-ID, State of Idaho INEL Oversight Program, US Geological Survey, and INEL employees to investigate three issues that had been identified by the INEL Oversight Program at ICPP: (1) the water inventory imbalance at ICPP, (2) the source of water infiltrating into the Tank Farm vault sumps, and (3) the source of water providing potential recharge to perched water bodies underlying ICPP. These issues suggested that water was being lost from the ICPP distribution system. The INEL Oversight Program was concerned that the unaccounted for water at ICPP could be spreading contaminants that have been released over the past 40 years of operations of ICPP, possibly to the Snake River Plain Aquifer. This report summarizes the findings of each of the component ...
1994-01-01
DOE personnel neutron dosimetry evaluation and upgrade program
Energy Technology Data Exchange (ETDEWEB)
The US Department of Energy (DOE) sponsors an extensive research program to improve the methods, dosimeters, and instruments available to DOE facilities for measuring neutron dose and assessing its effects on the work force. The Total Dose Meter was recently developed for measuring in real time the adsorbed dose of mixed neutron and gamma radiation and for calculating the dose equivalent. The Field Neutron Spectrometer was developed to provide a portable instrument for determining neutron spectra in the workplace for flux-to-dose equivalent conversion and quality factor calculation. The Combination Thermoluminescence/Track Etch Dosimeter (TLD/TED) was developed to extend the effective neutron energy range of the conventional TLDs to improve detection of fast-energy neutrons. An Optically Stimulated Luminescence Dosimeter is presently being developed for application to gamma, neutron, and beta radiation. An Effective Dose Equivalent System is ...
1988-10-01
Terra Nova Environmental effects monitoring program
Energy Technology Data Exchange (ETDEWEB)
Elements of the environmental effects monitoring program in the Terra Nova oil field, about 350 km east-southeast of St. John's, Newfoundland, are described. This oilfield is being developed using a floating production storage and offloading (FPSO) facility. A total of 24 wells are expected to be drilled through seven subsea templates located in four glory holes to protect them from icebergs. Subsea installations will be linked to the FPSO by trenched flowlines connected to flexible risers. The FPSO will offload to shuttle tankers. First oil is expected in 2001. The environmental effects monitoring program will be conducted annually for the first two years beginning in 2000. Subsequent scheduling will be determined after a review of monitoring data collected during the first three years. Input to the design of the monitoring program was provided by all stakeholders, i. e. owners, local public, ...
2000-07-01
Energy Technology Data Exchange (ETDEWEB)
The Outstanding Achievement Award in Water Pollution Control' is intended to recognize the water pollution control program that best demonstrates achieving significant, lasting, and measurable excellence in water-quality improvement in preventing water-quality degradation in a region, basin, or water body. This article is about the 1991 Award. This year, WPCF honored Los Angeles Hyperion Treatment Plant with a citation of outstanding achievement. To qualify for this honor, Hyperion has remarkably improved the quality of wastewater discharged to Santa Monica Bay since 1985. Capital programs developed by Los Angeles to achieve this rapid improvement, coined the Hyperion Improvement Program (HIP), reflect the city's commitment to protect the valuable resource of Santa Monica Bay. The HIP was conceived in 1986 to cease sludge ocean disposal by the end of 1987 and expedite effluent quality improvement before ...
1991-11-01
International Safeguards Technology and Policy Education and Training Pilot Programs
Energy Technology Data Exchange (ETDEWEB)
A major focus of the National Nuclear Security Administration-led Next Generation Safeguards Initiative (NGSI) is the development of human capital to meet present and future challenges to the safeguards regime. An effective university-level education in safeguards and related disciplines is an essential element in a layered strategy to rebuild the safeguards human resource capacity. NNSA launched two pilot programs in 2008 to develop university level courses and internships in association with James, Martin Center for Nonproliferation Studies (CNS) at the Monterey Institute of International Studies (MIIS) and Texas A&M University (TAMU). These pilot efforts involved 44 students in total and were closely linked to hands-on internships at Los Alamos National Laboratory (LANL) and Lawrence Livermore National Laboratory (LLNL). The Safeguards and Nuclear Material Management pilot program was a collaboration between TAMU, LANL, and LLNL. The ...
2009-06-16
Experiments with the HORUS-II test facility
Energy Technology Data Exchange (ETDEWEB)
Within the scope of the German reactor safety research the thermohydraulic computer code ATHLET which was developed for accident analyses of western nuclear power plants is more and more used for the accident analysis of VVER-plants particularly for VVER-440,V-213. The experiments with the HORUS-facilities and the analyses with the ATHLET-code have been realized at the Technical University Zittau/Goerlitz since 1991. The aim of the investigations was to improve and verify the condensation model particularly the correlations for the calculation of the heat transfer coefficients in the ATHLET-code for pure steam and steam-noncondensing gas mixtures in horizontal tubes. About 130 condensation experiments have been performed at the HORUS-II facility. The experiments have been carried out with pure steam as well as with noncondensing gas injections into the steam mass flow. The experimental simulations are characterized as ...
1997-12-31
Energy Technology Data Exchange (ETDEWEB)
This report is to present the progress made on the project ''Establishment of an Environmental Control Technology Laboratory (ECTL) with a Circulating Fluidized-Bed Combustion (CFBC) System'' during the period January 1, 2005 through March 31, 2005. The following tasks have been completed. First, the renovation of the new Combustion Laboratory is nearly complete, and the construction of the Circulating Fluidized-Bed (CFB) Combustor Building is in the final stages. Second, the fabrication and manufacture of the CFBC Facility is being discussed with a potential contractor. Discussions with potential contactor regarding the availability of materials and current machining capabilities have resulted in the modification of the original designs. The selection of the fabrication contractor for the CFBC Facility is expected during the next quarter. Third, co-firing experiments conducted with coal and chicken waste ...
2005-04-30
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 storage of spent fuel in ...
2002-04-01
Energy Technology Data Exchange (ETDEWEB)
The objective of this research was to determine the extent of damage that occurs when two pipes experience an impact event due to one whipping against the other. The research was conducted through experimental and analytical approaches. The former required the development of a specialized impact machine that could accelerate a whipping pipe with sufficient energy to cause failure of a target pipe that was heated and pressurized to Pressurized Water Reactor (PWR) conditions. Damage was measured in terms of crushing, bending, and failure. The results of the tests permitted the correlation between pipes of a certain size and the damage they could cause when impacting with a certain amount of known energy. These results were used to evaluate the pipe whip criteria in the Standard Review Plan 3.6.2-4. It was established that the criteria conditions did not fully represent the results obtained experimentally. An analysis procedure to model the pipe ...
1987-05-01
Experimental Seminar on Nuclear Energy for Teachers
Energy Technology Data Exchange (ETDEWEB)
`Experimental Seminar on Nuclear Energy for Teachers` was conducted and sponsored by the Science and Technology Agency. And in order to understand nuclear energy properly through lectures and experiments with good results inclass, the seminar carried out for teachers of high schools and junior high schools by the Nuclear Technology and Education Center (NuTEC), Japan Atomic Energy Research Institute in 1990 FY to 1997 FY. In this report, details of the seminars in the above period are described and No.1 to 17 of Communication Letters of Experimental Seminar on Nuclear Energy` started at 1992 FY are described also. These letters were prepared for attendant follow-up program. And programs of recent seminars, future`s seminars, impressions and comments from attendants, reports from actual classes and others are described in these letters and they are very useful for educational classes on nuclear energy by ...
1999-02-01
Resolving the Pu Electronic Structure Enigma: Past Lessons and Future Directions
Energy Technology Data Exchange (ETDEWEB)
The nature of the 5f electronic structure of plutonium (Pu) remains unclear. [1] Despite many recent attempts to resolve the issue, a plethora of important unanswered questions remain. While many theoretical approaches to the problem have been promulgated, the real source of the difficulty is the absence of sufficient experimental benchmarking. This paucity of impact on the part of experimental results is driven in part by the difficulties of working with Pu: it is highly radioactive, biologically toxic, chemically reactive and restricted in its distribution and permitted access to user facilities. The results of these liabilities include the following: (1) it is very difficult, if not impossible, to get large single crystals of single phase samples and; (2) many state of the art experiments can not be done because general user facilities are not available for use with Pu samples. Additionally, there is ...
2008-05-30
Natural circulation cooling in US Pressurized Water Reactors
International Nuclear Information System (INIS)
This document is a synthesis of data and analysis concerning natural circulation cooling in US Pressurized Water Reactors during off-normal operation and accident transients. Its objective is the integration of important research findings concerning PWR natural circulation phenomena into a single reference document. Sources of information include the Nuclear Regulatory Commission, reactor vendors, utility sponsored research groups, utilities, national laboratories, research reports, meeting papers, archival literature, and foreign sources. Three modes of natural circulation are discussed: single-phase, two-phase, and reflux/boiling condensation. General characteristics, analytical expressions, noncondensible gas effects, secondary effects, and nonuniform flow are described with regard to each of the natural circulation modes. Plant operational data, tests in scaled experimental facilities, and analysis with thermal hydraulic system codes have ...
Energy Technology Data Exchange (ETDEWEB)
This purpose of this report is to present the progress made on the project ''Establishment of an Environmental Control Technology Laboratory (ECTL) with a Circulating Fluidized-Bed Combustion (CFBC) System'' during the period April 1, 2005 through June 30, 2005. The following tasks have been completed. First, the new Combustion Laboratory was occupied on June 15, 2005, and the construction of the Circulating Fluidized-Bed (CFB) Combustor Building is in the final painting stage. Second, the fabrication and manufacturing contract for the CFBC Facility was awarded to Sterling Boiler & Mechanical, Inc. of Evansville, Indiana. Sterling is manufacturing the assembly and component parts of the CFBC system. The erection of the CFBC system is expected to start September 1, 2005. Third, mercury emissions from the cofiring of coal and chicken waste was studied experimentally in the laboratory-scale simulated ...
2005-07-30
Angular sensitivity distribution of detectors for BNCT
Energy Technology Data Exchange (ETDEWEB)
The research on the therapy of brain tumors and others by the thermal neutron irradiation using research reactors is to kill tumor cells by accumulating boron at a tumor part, and using {alpha} particles and {sup 7}Li generated by {sup 10}B(n, {alpha}){sup 7}Li reaction of thermal neutrons, which is known as boron neutron capture therapy (BNCT). In Japan Atomic Energy Research Institute, the medical irradiation facility was installed in the thermal neutron column of the JRR-2, and as of March, 1994, 22 cases of irradiation have been carried out. In order to monitor the variation of thermal neutron flux during irradiation, the real time measurement using a simultaneous monitor is carried out, but there is the variation of measured values in the Si semiconductor, p-n junction detector possibly due to its direction dependence. The experiment was carried out to quantity the direction dependence of the detector by using the neutron radiography ...
1995-03-01
Energy Technology Data Exchange (ETDEWEB)
Isobaric contaminants are often problematical in accelerated negative ion beams for research at certain radioactive ion beam (RIB) and accelerator mass spectrometry (AMS) facilities since their presence in low-intensity rare isotopic beams seriously compromise experimental results. This article describes a non-resonant, laser-based photo-detachment apparatus for use at these facilities, which, according to calculations efficiently removes isobaric contaminants from these beams. The advantage of the system for isobaric contaminant removal over other systems proposed to date lies in its ability to efficiently capture easily transportable energetic negative ion beams with low, intermediate or high energy spreads by a superconducting solenoid magnetic field. The ability to change the diameter of captured beams by adjusting the magnetic field strength permits optimum control of the radial overlap of the laser/negative ion beam ...
2008-09-01
University of Central Lancashire - Facilities
...specialised laboratories for pharmaceutics, tissue culture and molecular biology Excellent Laboratory Facilities Tissue Culture Facilities Molecular Biology Laboratory ...
Energy Technology Data Exchange (ETDEWEB)
Previous reports have stressed the importance of the nutrient blood supply in rib grafts transferred by microvascular anastomoses. In the present experimental study, we have demonstrated that a rib graft transferred by microvascular anastomoses based on periosteal vessels can survive; vascular clearing studies demonstrated that the vascularity of these grafts extends not only into the cortex but the medulla as well. The relative facility of harvesting these grafts (compared with those based on nutrient vessels) should make them the favored choice. Technetium bone scintigraphy proved accurate in the assessment of both vascular pattern and microanastomotic patency. Tetracycline labeling did not correlate well with the patency of a rib graft's pedicle blood supply.
1984-11-01
On the role of the Jeffreys'sheltering mechanism in the sustain of extreme water waves
The effect of the wind on the sustain of extreme water waves is investigated experimentally and numerically. A series of experiments conducted in the Large Air-Sea Interactions Facility (LASIF) showed that a wind blowing over a strongly nonlinear short wave group due to the linear focusing of a modulated wave train may increase the life time of the extreme wave event. The expriments suggested that the air flow separation that occurs on the leeward side of the steep crests may sustain longer the maximum of modulation of the focusing-defocusing cycle. Based on a Boundary-Integral Equation Method and a pressure distribution over the steep crests given by the Jeffreys'sheltering theory, similar numerical simulations have confirmed the experimental results
2006-01-01
Development of a small scintillation detector with an optical fiber for fast neutrons
International Nuclear Information System (INIS)
To investigate the characteristics of a reactor and a neutron generator, a small scintillation detector with an optical fiber with ThO_2 has been developed to measure fast neutrons. However, experimental facilities where "2"3"2Th can be used are limited by regulations, and S/N ratio is low because the background counts of this detector are increase by alpha decay of "2"3"2Th. The purpose of this study is to develop a new optical fiber detector for measuring fast neutrons that does not use nuclear material such as "2"3"2Th. From the measured and calculated results, the new optical fiber detector which uses ZnS(Ag) as a converter material together with a scintillator have the highest detection efficiency among several developed detectors. It is applied for the measurement of reaction rates generated from fast neutrons; furthermore, the absolute detection efficiency of this detector was obtained experimentally.
2011-02-01
Application of probabilistic methods to validate NPP pipewhip impact simulations
British Library Electronic Table of Contents (United Kingdom)
Piping in nuclear power plants is vital to the proper operation and safety of these facilities. To assure safety in the unlikely event of a pipe break, it is necessary to evaluate the consequences from the resulting whipping pipe on neighboring components and structures. Numerical simulations allow for rapid evaluation of these consequences. Before simulations can be accepted, however, the methodology and computer codes must be validated against experimental results. This paper uses a probabilistic approach to validate pipe whip simulations against limited experimental results. Probabilistic analysis software was developed and coupled to existing deterministic finite element software. An example of a whipping pipe impacting against a reinforced concrete slab was simulated. The described pr...
2006-01-01
Applicability of structural wall test results to seismic design of nuclear facilities
International Nuclear Information System (INIS)
A review of tests on earthquake-resistant reinforced concrete structural walls is presented. Laboratory tests of isolated walls and construction joints are discussed. Where appropriate, design recommendations are given. The review indicates only few experimental data are available for short walls which are directly applicable to nuclear power plant design. In particular, tests of short rectangular walls subjected to load reversals are needed. Tests are also needed to determine the damping and frequency characteristics of cracked short walls. Analytical and experimental results should be correlated so that the hysteretic response observed in tests can be realistically related to the analytical response 'demand' of nuclear power plant structures. (Auth.).
Mercury flow experiments. 3. Simulation test plan under abnormal condition
Energy Technology Data Exchange (ETDEWEB)
Japan Atomic Energy Research Institute (JAERI) and High Energy Accelerator Research Organization (KEK) are promoting construction plan of Material-Life Science Facility, which is consisted of Muon Science Facility and Neutron Scattering Facility, in order to open up the new science fields. The Neutron Scattering Facility will be utilized for advanced fields of Material and Life science using high intensity neutrons generated by the spallation reaction induced by injecting a 1 MW pulsed proton beam onto a mercury target. Design of the spallation mercury target system is in progress to obtain good neutron performance keeping high reliability and safety. The target material is mercury. As a result of the spallation reaction, large amount of radioactive spallation products are to be contained in the mercury. Therefore to establish the safety of the target system, transient behaviors of the system during ...
2002-02-01
Overview of the US coal liquefaction program
The US Department of Energy is carrying out a program of research and development to establish the capability to produce synthetic liquid fuels from coal. According to the National Energy Policy Plan IV, the Assistant Secretary of Fossil Energy is charged with carrying out a program to foster an adequate supply of energy at reasonable cost through innovative, long-term R and D. The payoff for this kind of research is potentially high if the country should need the capability on short notice. However, the research is also high risk in terms of the expectation of process for synthetic fuels to turn a profit for a private sector company. As the date when commercial quantities of synfuels will be needed has retreated before lower real prices of petroleum, the US DOE program for coal liquefaction has evolved to give increasing support to longer range, more exploratory technologies, rather than those nearly developed to the point ...
1986-03-01
FastFlow: Efficient Parallel Streaming Applications on Multi-core
Shared memory multiprocessors come back to popularity thanks to rapid spreading of commodity multi-core architectures. As ever, shared memory programs are fairly easy to write and quite hard to optimise; providing multi-core programmers with optimising tools and programming frameworks is a nowadays challenge. Few efforts have been done to support effective streaming applications on these architectures. In this paper we introduce FastFlow, a low-level programming framework based on lock-free queues explicitly designed to support high-level languages for streaming applications. We compare FastFlow with state-of-the-art programming frameworks such as Cilk, OpenMP, and Intel TBB. We experimentally demonstrate that FastFlow is always more efficient than all of them in a set of micro-benchmarks and on a real world application; the speedup edge of FastFlow over other solutions might be ...
2009-01-01
Studies of Plasma Confinement in GOL-3 Multi-mirror Trap
International Nuclear Information System (INIS)
Recent results of the experiments at GOL-3 facility are presented. Plasma with a density of 1014...1016 cm-3 is confined in a 12-meter-long solenoid, which comprises 55 corrugation cells with mirror ratio Bmax/B min=4.8/3.2 T. The plasma is heated up to 2...4 keV temperature by a high power relativistic electron beam (?1 MeV, ? 330 kA, ?8?s, ?120 kJ) injected through one of the ends. Mechanism of experimentally observed fast ion heating, issued of plasma stability and confinement are discussed.
2006-01-01
Energy Technology Data Exchange (ETDEWEB)
The report covers the results of exposing materials for steam turbines to increased steam temperatures in two modules of the KOMET 650 testing facility at the Westfalen power plant. Ferritic/martensitic steels with 9 to 12% Cr and austenite and nickel-based alloys were investigated. Some experimental coatings on low-alloy Cr steel were also tested. The principal findings are presented. It will become possible to construct advanced power stations to be operated at higher temperatures. (orig.)
2008-07-01
Demonstration experiment on improved radwaste evaporator
Energy Technology Data Exchange (ETDEWEB)
High conductivity liquid waste, which is produced in nuclear power plants, is now processed with radwaste evaporator. The concentrated liquid waste in the evaporator is so highly radioactive and corrosive that the improvement on maintenability and reduction of exposure dose rate are desirable as well as high decontamination factor (DF). Fuji Electric constructed the improved experimental facility of evaporator and carried out an experiment to demonstrate DF, maintenability and controllability of system. As the results, DF, maintenability and controllability were proved to be excellent and its applicability to nuclear power plant was well established.
1988-07-01
Combustion performance of Coal Valley coal in a pilot-scale utility boiler. Report No. ERL 87-18(CF)
Energy Technology Data Exchange (ETDEWEB)
Combustion performance trials were conducted on a commercial sample of Coal Valley coal from the Coalspur coalfield in the foothills region of Alberta. The project included an analytical investigation of the coal and coal ash properties as well as combustion studies in the CCRL pilot-scale, pulverized coal-fired boiler, under conditions representative of those in large steam boilers. This report gives the objectives of the project, the analyses of the coals, and describes the facilities and operational procedures. An evaluation of the experimental results and the conclusions are presented.
1987-01-01
Individual Radiation Protection Monitoring in the Marshall Islands: Rongelap Atoll (2002-2004)
Energy Technology Data Exchange (ETDEWEB)
The United States Department of Energy (U.S. DOE) has recently implemented a series of strategic initiatives to address long-term radiological surveillance needs at former U.S. nuclear test sites in the Marshall Islands. The plan is to engage local atoll communities in developing shared responsibilities for implementing radiation protection monitoring programs for resettled and resettling populations in the northern Marshall Islands. Using the pooled resources of the U.S. DOE and local atoll governments, individual radiological surveillance programs have been developed in whole body counting and plutonium urinalysis in order to accurately assess radiation doses resulting from the ingestion and uptake of fallout radionuclides contained in locally grown foods. Permanent whole body counting facilities have been established at three separate locations in the Marshall Islands including Rongelap Atoll (Figure 1). These ...
2006-01-17
Energy Technology Data Exchange (ETDEWEB)
ENEA (Italian National Agency for New Technologies, Energy and the Environment) is conducting a large research and development programme on innovative vehicles with high energy efficiency and low environmental impact. In particular conducts activities on electric and hybrid vehicles. Testing and evaluation activities play a strong role in this programme. A complete characterization chain has been then defined and set up with a network of facilities which covers main testing needs for single components, subsystems and complete vehicles, in simulated and real operating conditions. The test facility which has been realised is able to experiment and fully characterise complete drive-trains (and subsystems) for pure electric and hybrid vehicles. It is composed by a different section for each subsystem: 1) power generation; 2) energy storage and management; 3) driving motors. Each section acts as an experimental island, able to ...
1998-12-31
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 temporarily, but they would significantly ...
1995-04-01
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 significantly reduce its capabilities to ...
1995-08-01
Energy Technology Data Exchange (ETDEWEB)
Program activities and achievements in 1982 of the geodynamic program are summarized. The significant results presented are summarized.
1983-05-01
International Nuclear Information System (INIS)
This plan establishes both the scope of the review and the acceptance criteria to be utilized for the review of Quality Assurance Program Plans (QAPPs) developed in accordance with the requirements of DOE/RL-90-28. DOE/RL-90-28, the Environmental Restoration Remedial Action Quality Assurance Requirements Document (QARD) defines all quality assurance (QA) requirements governing activities that affect the quality of the Environmental Restoration Remedial Action (ERRA) program at the Hanford Site. These requirements are defined in three parts, Part 1 of Quality Management and Administration tasks, Part 2 for Environmental Data Operations, and Part 3 of the Design and Construction of items, systems, and facilities. The purpose of this document is to identify the scope of the review by the DOE Field Office, Richland staff, and establish the acceptance criteria (Parts 1, 2, and 3) that the DOE Field Office, Richland staff will ...
Routine environmental audit of the Y-12 Plant, Oak Ridge, Tennessee
Energy Technology Data Exchange (ETDEWEB)
This report documents the results of the routine environmental audit of the Oak Ridge Y-12 Plant (Y-12 Plant), Anderson County, Tennessee. During this audit, the activities conducted by the audit team included reviews of internal documents and reports from previous audits and assessments; interviews with U.S. Department of Energy (DOE), State of Tennessee regulatory, and contractor personnel; and inspections and observations of selected facilities and operations. The onsite portion of the audit was conducted August 22-September 2, 1994, by the DOE Office of Environmental Audit (EH-24), located within the Office of Environment, Safety and Health (EH). DOE 5482.1 B, {open_quotes}Environment, Safety, and Health Appraisal Program,{close_quotes} establishes the mission of EH-24 to provide comprehensive, independent oversight of DOE environmental programs on behalf of the Secretary of Energy. The ultimate goal of EH-24 is ...
1994-09-01
Energy Technology Data Exchange (ETDEWEB)
The US DOE manages the safe storage of approximately 650,000 tons of depleted uranium hexafluoride remaining from the Cold War. This slightly radioactive, but chemically active, material is contained in more than 46,000 steel storage cylinders that are located at Oak Ridge, Tennessee; Paducah, Kentucky; and Portsmouth, Ohio. Some of the cylinders are more than 40 years old, and approximately 17,500 are considered problem cylinders because their physical integrity is questionable. These cylinders require an annual visual inspection. The remainder of the 46,000-plus cylinders must be visually inspected every four years. Currently, the cylinder inspection program is extremely labor intensive. Because these inspections are accomplished visually, they may not be effective in the early detection of leaking cylinders. The inspection program requires approximately 12--14 full-time-equivalent (FTE) employees. At the cost of approximately $125K per FTE, ...
1997-02-01
Maintenance implementation plan for solid waste management
Energy Technology Data Exchange (ETDEWEB)
This Maintenance Implementation Plan (MIP)was developed for implementation of the U.S. Department of Energy (DOE) Order 4330.4A, A Maintenance Implementation Program (DOE 1990) which has been replaced by 4330.4B (DOE 1994) at the Hanford Site SWM complex. It addresses maintenance functions associated with SWM, which includes the field operational group and the facilities operational group. An assessment of the existing maintenance programs for SWM 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 objective of this MIP is to provide baseline information for the control and execution of SWM Maintenance activities relative to the requirements of Order 4330.4B, Chapter II. (Nuclear Facilities) It also describes actions that are planned to achieve compliance. Section 2.0 of this MIP ...
1996-06-27
Geothermal heat cycle research: Supercritical cycle with horizontal counterflow condenser
Energy Technology Data Exchange (ETDEWEB)
The Heat Cycle Research Program, which is being conducted for the Department of Energy, has as its objective the development of the technology for effecting the improved utilization of moderate temperature geothermal resources. To meet this objective, the program has as one of its goals to improve the performance of geothermal binary cycles to levels approaching the practicable thermodynamic maximum. In pursuit of this goal, tests are being conducted at the Heat Cycle Research Facility located at the DOE Geothermal Test Facility, East Mesa, California. The current testing involves the investigation of binary power cycle performance utilizing mixtures of non-adjacent hydrocarbons as the working fluids, with supercritical vaporization and in-tube condensation of the working fluid. In addition to the present test program, preparations are being made to investigate the binary cycle ...
1987-01-01
The Darrieus-type Vertical Axis Wind Turbine (VAWT) presents a variety of unusual structural problems to designers. The level of understanding of these structural problems governs, to a large degree, the success or failure of today's rotor designs. A survey is presented of the technology available for rotor structural design with emphasis on the DOE research program now underway. Itemizations are included of the major structural issues unique to the VAWT along with discussion of available analysis techniques for each problem area. It is concluded that tools are available to at least approximately address the most important problems. However, experimental data for confirmation is rather limited in terms of volume and the range of rotor configurations tested.
1982-01-01
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
KLOE-2 experiment at DA$\\Phi$NE upgraded in luminosity
Prospective presentation is given for the experimental program of the KLOE-2 Collaboration, to be performed using the DA$\\Phi$NE $e^+e^-$ collider upgraded in luminosity. Data with the total luminosity of 25 fb$^{-1}$ are aimed to be collected in 3 years. Major modifications of the accelerator and the spectrometer are described. The KLOE-2 physics program contains: CKM unitarity and lepton universality tests, $\\gamma\\gamma$ physics, search for quantum decoherence and testing CPT conservation, low-energy QCD, rare kaon decays, physics of $\\eta$ and $\\eta^\\prime$, structure of low-mass scalars, contribution of vacuum polarization to $(g-2)_{\\mu}$, possible search for WIMP dark matter. In this paper only selected physics subjects are reported.
2011-01-01
Energy Technology Data Exchange (ETDEWEB)
The program introduced here for determining and describing the multi-axial creep of pipes is based, on the one hand, on the results of the nuclear process heat prototype plant material program and, on the other hand, on the possible load conditions which arise for evaluating accidents or extreme working situations. The basis of a theoretical description of multi-axial creep is the invariant theory in which both the von Mises configuration change hypothesis and the Norton creep law are included. Combined tension and torsion are also considered in detail, the superimposition of cyclic stresses in the tensile threshold area is discussed and cases of partial relaxation are explained. Experimental results for the discussed loads are introduced, which have led to satisfactory agreement between theory and experiment. (orig./MM).
1987-01-01
International Nuclear Information System (INIS)
The program introduced here for determining and describing the multi-axial creep of pipes is based, on the one hand, on the results of the nuclear process heat prototype plant material program and, on the other hand, on the possible load conditions which arise for evaluating accidents or extreme working situations. The basis of a theoretical description of multi-axial creep is the invariant theory in which both the von Mises configuration change hypothesis and the Norton creep law are included. Combined tension and torsion are also considered in detail, the superimposition of cyclic stresses in the tensile threshold area is discussed and cases of partial relaxation are explained. Experimental results for the discussed loads are introduced, which have led to satisfactory agreement between theory and experiment. (orig./MM).
1987-11-27
Health and Safety Research Division progress report for the period April 1, 1987--September 30, 1988
Energy Technology Data Exchange (ETDEWEB)
The mission of the Health and Safety Research Division (HASRD) is to provide a sound scientific basis for the measurement and assessment of human health impacts of radiological and chemical substances. Our approach to fulfilling this mission is to conduct a broad program of experimental, theoretical, and field research based on a strong foundation of fundamental physical studies that blend into well-established programs in life sciences. Topics include biomedical screening techniques, biological and chemical sensors, risk assessment, health hazards, dosimetry, nuclear medicine, environmental pollution monitoring, electron-molecule interactions, interphase physics, surface physics, data base management, environmental mutagens, carcinogens, and tetratogens.
1989-03-01
Summary of Information and Resources Related to Energy Use in Healthcare Facilities - Version 1
Energy Technology Data Exchange (ETDEWEB)
This document presents the results of a review of publicly available information on energy use in health care facilities. The information contained in this document and in the sources cited herein provides the background and context for efforts to reduce energy use and costs in health care. Recognizing the breadth and diversity of relevant information, the author acknowledges that the report is likely not comprehensive. It is intended only to present a broad picture of what is currently known about health care energy use. This review was conducted as part of a 'High Performance Health Care Buildings' research study funded by the California Energy Commission. The study was motivated by the recognition that health care facilities collectively account for a substantial fraction of total commercial building energy use, due in large part to the very high energy intensity of hospitals and other inpatient care ...
2009-09-08
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 ...
Energy Technology Data Exchange (ETDEWEB)
This Site Maintenance Plan has been developed for Pacific Northwest Laboratory's (PNL) Nonnuclear Facilities. It is based on requirements specified by US Department of Energy (DOE) Order 4330.4A, Chapter I, Change No. 4. The objective of this maintenance plan is to provide baseline information for compliance to the DOE Order 4330.4A, to identify needed improvements, and to document the planned maintenance budget for Fiscal Year (FY) 1993 and to estimate maintenance budgets for FY 1994 and FY 1995 for all PNL facilities. Using the results of the self-assessment, PNL has selected 12 of the 36 elements of the Maintenance Program defined by DOE Order 4330.4A, Chapter I, for improvement. The elements selected for improvement are: Facility Condition Inspections; Work Request (Order) System; Formal Job Planning and Estimating; Work Performance (Time) Standards; Priority System; Maintenance Procedures ...
1992-09-28
Energy Technology Data Exchange (ETDEWEB)
This Site Maintenance Plan has been developed for Pacific Northwest Laboratory`s (PNL) Nonnuclear Facilities. It is based on requirements specified by US Department of Energy (DOE) Order 4330.4A, Chapter I, Change No. 4. The objective of this maintenance plan is to provide baseline information for compliance to the DOE Order 4330.4A, to identify needed improvements, and to document the planned maintenance budget for Fiscal Year (FY) 1993 and to estimate maintenance budgets for FY 1994 and FY 1995 for all PNL facilities. Using the results of the self-assessment, PNL has selected 12 of the 36 elements of the Maintenance Program defined by DOE Order 4330.4A, Chapter I, for improvement. The elements selected for improvement are: Facility Condition Inspections; Work Request (Order) System; Formal Job Planning and Estimating; Work Performance (Time) Standards; Priority System; Maintenance Procedures and Other ...
1992-09-28
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 ...
1993-12-01
Geothermal materials program: strategy. Final report
Energy Technology Data Exchange (ETDEWEB)
The following topics are discussed: program goal and objectives, program organization, and program status. Current program projects are described. (MHR)
1980-10-01
Storing hydroelectricity to meet peak-hour demand
Energy Technology Data Exchange (ETDEWEB)
This paper reports on pumped storage plants which have become an effective way for some utility companies that derive power from hydroelectric facilities to economically store baseload energy during off-peak hours for use during peak hourly demands. According to the Electric Power Research Institute (EPRI) in Palo Alto, Calif., 36 of these plants provide approximately 20 gigawatts, or about 3 percent of U.S. generating capacity. During peak-demand periods, utilities are often stretched beyond their capacity to provide power and must therefore purchase it from neighboring utilities. Building new baseload power plants, typically nuclear or coal-fired facilities that run 24 hours per day seven days a week, is expensive, about $1500 per kilowatt, according to Robert Schainker, program manager for energy storage at the EPRI. Schainker the that building peaking plants at $400 per kilowatt, which run a few hours a day on gas or ...
1992-04-01
Storing hydroelectricity to meet peak-hour demand
International Nuclear Information System (INIS)
This paper reports on pumped storage plants which have become an effective way for some utility companies that derive power from hydroelectric facilities to economically store baseload energy during off-peak hours for use during peak hourly demands. According to the Electric Power Research Institute (EPRI) in Palo Alto, Calif., 36 of these plants provide approximately 20 gigawatts, or about 3 percent of U.S. generating capacity. During peak-demand periods, utilities are often stretched beyond their capacity to provide power and must therefore purchase it from neighboring utilities. Building new baseload power plants, typically nuclear or coal-fired facilities that run 24 hours per day seven days a week, is expensive, about $1500 per kilowatt, according to Robert Schainker, program manager for energy storage at the EPRI. Schainker the that building peaking plants at $400 per kilowatt, which run a few hours a day on gas or ...
1992-01-01
Slide Rule for Rapid Response Estimation of Radiological Dose from Criticality Accidents
Energy Technology Data Exchange (ETDEWEB)
This paper describes a functional slide rule that provides a readily usable ?in-hand? method for estimating nuclear criticality accident information from sliding graphs, thereby permitting (1) the rapid estimation of pertinent criticality accident information without laborious or sophisticated calculations in a nuclear criticality emergency situation, (2) the appraisal of potential fission yields and external personnel radiation exposures for facility safety analyses, and (3) a technical basis for emergency preparedness and training programs at nonreactor nuclear facilities. The slide rule permits the estimation of neutron and gamma dose rates and integrated doses based upon estimated fission yields, distance from the fission source, and time-after criticality accidents for five different critical systems. Another sliding graph permits the estimation of critical solution fission yields based upon fissile material ...
1999-09-20
Low temperature irradiations in FFTF [Fast Flux Test Facility
International Nuclear Information System (INIS)
The fusion materials program has little irradiation effects data at temperatures from 100 to 350 degree C. Near-term machines such as the International Thermonuclear Engineering Reactor (ITER) will expose materials to neutron doses of 38 to 50 dpa at 150 degree C or less. The data base for structural materials must be extended into this range. Also, lower temperatures are needed to investigate the lower bound for tritium release from solid breeder materials. A low temperature test vehicle is proposed for the Fast Flux Test Facility (FFTF), which will provide test temperatures of 100 to 350 degree C. An 8.5-cm dia. by 100-cm test volume will be instrumented to collect temperature data and provide feedback for control. The spectrum and flux will provide accelerated damage accumulation for structural materials testing and the best available approximation of fusion reactor conditions for solid breeder materials testing. Breeder samples can be ...
1988-10-09
Energy Technology Data Exchange (ETDEWEB)
Test Area North (TAN) was a site of the Aircraft Nuclear Propulsion (ANP) Project of the U.S. Air Force and the Atomic Energy Commission. Its Cold War mission was to develop a turbojet bomber propelled by nuclear power. The project was part of an arms race. Test activities took place in five areas at TAN. The Assembly & Maintenance area was a shop and hot cell complex. Nuclear tests ran at the Initial Engine Test area. Low-power test reactors operated at a third cluster. The fourth area was for Administration. A Flight Engine Test facility (hangar) was built to house the anticipated nuclear-powered aircraft. Experiments between 1955-1961 proved that a nuclear reactor could power a jet engine, but President John F. Kennedy canceled the project in March 1961. ANP facilities were adapted for new reactor projects, the most important of which were Loss of Fluid Tests (LOFT), part of an international safety program for ...
2005-02-01
Evolutionary developments advancing the floating production, storage, and offloading concept
Energy Technology Data Exchange (ETDEWEB)
Tanker-based floating production, storage, and offloading (FPSO) systems have been in operation since Aug. 1977, when a single-well FPSO facility was put into production by Shell Espana in the Mediterranean. The overall operational experience with this system at this field is reviewed, with special attention to the wireline workover facilities, which have proved very satisfactory. A subsequent evolutionary step, a FPSO system accommodating multiple wells, necessitated development of a multibore fluid swivel. A design program for this swivel was initiated in 1978; a prototype was built and full-scale testing finalized in 1980. A summary of the test results is presented. Simultaneously with the multibore swivel development, detailed engineering for an eight-well FPSO unit was begun. This system includes gas-lift and water injection capabilities. Provisions for through-flowline (TFL) well workover can be incorporated. The ...
1983-04-01
Energy Engineering Analysis Program Limited Energy Study, Fort Hunter-Liggett, California. Volume 1
The purpose of this study is to develop projects and actions that will reduce facilities energy consumption and operating costs at Fort Hunter Liggett. Implementation of these projects will contribute to achieving the goal of the Army Facilities Energy Plan of a reduction in energy consumption per square foot of building floor area of 20 percent by FY2OOO from FY1985 baseline levels, There are 205 numbered structures at Fort Hunter Liggett, containing a total of 791,034 square feet of gross floor space. This United Energy Study evaluates 52 surveyed buildings with results extended to an additional 44 identical or similar buildings. Together, these buildings contain a total of 632,386 gross square feet and account for approximately 93 percent of overall energy usage. Present Energy Consumption Total energy consumption at Fort Hunter Ligett in FY 1992 of non-transportation energy sources was 79,728 million Btu. This figure includes electricity at ...
1993-12-31
Energy Technology Data Exchange (ETDEWEB)
The objective of this Energy Engineering Analysis (EEA) for LSAAP is threefold: Develop a systematic plan of projects which will result in reducing energy consumption. Consider renewable energy sources with the objective of establishing an orderly procedure for reducing use of non-renewable energy sources. Determine the feasibility of Total Energy (TE), Selective Energy (SE), and Central Heating Plant (CHP) concepts using alternative fuels. In essence, an assessment of the entire energy picture at LSAAP was undertaken. This report is a summary of that effort. LSAAP was originally built during 1941 and 1942 as a shell loading plant for the Army. After World War II, the facility was deactivated until 1951 when it was reactivated as a Government Owned, Contractor Operated (GOCO) facility. Day and Zimmerman was selected as the operator in 1951 and has been the operating contractor ever since. Located just west of Texarkana, Texas, LSAAP encompasses ...
1981-12-31
Energy Technology Data Exchange (ETDEWEB)
This report identifies individual contaminants and contaminant mixtures that have been measured in the ground at 91 waste sites at 18 US Department of Energy (DOE) facilities within the weapons complex. The inventory of chemicals and mixtures was used to identify generic chemical mixtures to be used by DOE's Subsurface Science Program in basic research on the subsurface geochemical and microbiological behavior of mixed contaminants (DOE 1990a and b). The generic mixtures contain specific radionuclides, metals, organic ligands, organic solvents, fuel hydrocarbons, and polychlorinated biphenyls (PCBs) in various binary and ternary combinations. The mixtures are representative of in-ground contaminant associations at DOE facilities that are likely to exhibit complex geochemical behavior as a result of intercontaminant reactions and/or microbiologic activity stimulated by organic substances. Use of the generic mixtures ...
1992-04-01
Energy Technology Data Exchange (ETDEWEB)
During the early years of the INEL, the USGS conducted extensive studies (sitewide drilling program) of the geology and hydrology of the area collecting varied data over the years. The unsaturated zone has not received much attention until recently. The studies that have been done are a result of problems or concerns arising from liquid radioactive waste disposal. The TRA facility has the most information published about its waste disposal activities. The ICPP has less data about the unsaturated zone due to the fact that most waste water disposal has been to a well. Little is known about the effect of waste water disposal at the NRF on the unsaturated zone. Essentially no information was found about waste disposal activities at other facilities, primarily because there does not appear to be any reported problems associated with waste water disposal at these locations. The RWMC has received much attention in the last few ...
1992-01-01
Energy Technology Data Exchange (ETDEWEB)
During the early years of the INEL, the USGS conducted extensive studies (sitewide drilling program) of the geology and hydrology of the area collecting varied data over the years. The unsaturated zone has not received much attention until recently. The studies that have been done are a result of problems or concerns arising from liquid radioactive waste disposal. The TRA facility has the most information published about its waste disposal activities. The ICPP has less data about the unsaturated zone due to the fact that most waste water disposal has been to a well. Little is known about the effect of waste water disposal at the NRF on the unsaturated zone. Essentially no information was found about waste disposal activities at other facilities, primarily because there does not appear to be any reported problems associated with waste water disposal at these locations. The RWMC has received much attention in the last few ...
1992-12-31
Application of probabilistic methods to validate NPP pipewhip impact simulations
Energy Technology Data Exchange (ETDEWEB)
Piping in nuclear power plants is vital to the proper operation and safety of these facilities. To assure safety in the unlikely event of a pipe break, it is necessary to evaluate the consequences from the resulting whipping pipe on neighboring components and structures. Numerical simulations allow for rapid evaluation of these consequences. Before simulations can be accepted, however, the methodology and computer codes must be validated against experimental results. This paper uses a probabilistic approach to validate pipe whip simulations against limited experimental results. Probabilistic analysis software was developed and coupled to existing deterministic finite element software. An example of a whipping pipe impacting against a reinforced concrete slab was simulated. The described probabilistic approach was used to validate the numerical simulations. The conclusions obtained were that the numerical simulations of ...
2006-02-15
Automated Critical Peak Pricing Field Tests: Program Descriptionand Results
Energy Technology Data Exchange (ETDEWEB)
California utilities have been exploring the use of critical peak prices (CPP) to help reduce needle peaks in customer end-use loads. CPP is a form of price-responsive demand response (DR). Recent experience has shown that customers have limited knowledge of how to operate their facilities in order to reduce their electricity costs under CPP (Quantum 2004). While the lack of knowledge about how to develop and implement DR control strategies is a barrier to participation in DR programs like CPP, another barrier is the lack of automation of DR systems. During 2003 and 2004, the PIER Demand Response Research Center (DRRC) conducted a series of tests of fully automated electric demand response (Auto-DR) at 18 facilities. Overall, the average of the site-specific average coincident demand reductions was 8% from a variety of building types and facilities. Many electricity customers have suggested that ...
2006-04-06
Glass Furnace Combustion and Melting Research Facility.
Energy Technology Data Exchange (ETDEWEB)
The need for a Combustion and Melting Research Facility focused on the solution of glass manufacturing problems common to all segments of the glass industry was given high priority in the earliest version of the Glass Industry Technology Roadmap (Eisenhauer et al., 1997). Visteon Glass Systems and, later, PPG Industries proposed to meet this requirement, in partnership with the DOE/OIT Glass Program and Sandia National Laboratories, by designing and building a research furnace equipped with state-of-the-art diagnostics in the DOE Combustion Research Facility located at the Sandia site in Livermore, CA. Input on the configuration and objectives of the facility was sought from the entire industry by a variety of routes: (1) through a survey distributed to industry leaders by GMIC, (2) by conducting an open workshop following the OIT Glass Industry Project Review in September 1999, (3) from discussions ...
2004-08-01
Role of FFTF in assessing structural feedbacks and inherent safety of LMR's
International Nuclear Information System (INIS)
The possibility of developing reactor designs with inherent safety characteristics sufficient to provide walk away safety is receiving additional emphasis in the LMR program. A key element in this effort is the recognition that LMR's possess safety characteristics above and beyond those employed in past safety review processes. Some of these additional safety characteristics are due to reactivity feedback effects caused by small structural movements during hypothetical severe design transients. The effects of these characteristics upon the behavior of the FFTF under such transients has been assessed and is discussed in this paper. The paper also presents a preliminary test matrix which might allow experimental verification of the structural reactivity feedback effects. Such experimental verification should be very useful to innovative designers seeking to optimize inherent safety.
1985-07-01
Role of FFTF in assessing structural feedbacks and inherent safety of LMR's
International Nuclear Information System (INIS)
The possibility of developing reactor designs with inherent safety characteristics sufficient to provide ''walk away'' safety is receiving additional emphasis in the LMR program. A key element in this effort is the recognition that LMR's possess safety characteristics above and beyond those employed in past safety review processes. Some of these additional safety characteristics are due to reactivity feedback effects caused by small structural movements during hypothetical severe design transients. The effect of these characteristics upon the behavior of the FFTF under such transients has been assessed and is discussed in this paper. The paper also presents a preliminary test matrix which might allow experimental verification of the structural reactivity feedback effects. Such experimental verification should be very useful to innovative designers seeking to optimize inherent safety. 8 refs., 1 fig., 2 tabs.
1985-04-21
International Nuclear Information System (INIS)
Ppercase(femaxi-iv) is a computer code for the analysis of thermal and mechanical behavior of light water reactor fuel rods during steady-state and transient conditions. The main purpose of ppercase(femaxi-iv) is to calculate the stress and strain distributions in the fuel and cladding due to the pellet-cladding mechanical interaction, and the fission gas release rate during operations, especially power transients. The capability of ppercase(femaxi-iv) was extensively tested with a number of experimental results obtained in some international fuel irradiation programs. This paper provides a general description of the various models involved in ppercase(femaxi-iv) and some results of applications on the experimental data. ((orig.)).
1994-01-01
Energy Technology Data Exchange (ETDEWEB)
Femaxi-iv is a computer code for the analysis of thermal and mechanical behavior of light water reactor fuel rods during steady-state and transient conditions. The main purpose of femaxi-iv is to calculate the stress and strain distributions in the fuel and cladding due to the pellet-cladding mechanical interaction, and the fission gas release rate during operations, especially power transients. The capability of femaxi-iv was extensively tested with a number of experimental results obtained in some international fuel irradiation programs. This paper provides a general description of the various models involved in femaxi-iv and some results of applications on the experimental data. ((orig.))
1994-06-01
Analytical studies of four-inch pipe whip tests under BWR LOCA conditions
Energy Technology Data Exchange (ETDEWEB)
The purpose of pipe rupture studies in JAERI is to perform model tests on pipe whip, restraint behavior, jet impingement and jet thrust force, and to establish a computational method for analyzing these phenomena. This report presents the analytical results of 4-inch pipe whip tests under BWR LOCA conditions. Dynamic response analyses were performed using the general-purpose finite element program ADINA. The test pipe was modelled by straight beam elements and the four restraints were modelled by a single truss element. The analytical results were compared with the experimental results. Impact time and maximum total restraint force showed good agreement with experimental results. On the other hand, pipe strain and pipe deflection could not be predicted so well. The reason for this is that the sliding of the restraint during the pipe whip movement cannot be considered in the analyses.
1985-01-01
Relevance of mixed layer scaling for daytime dispersion based on RAPS and other field programs
Energy Technology Data Exchange (ETDEWEB)
A brief review and assessment of field measurement programs that provide data for mixed layer diffusion research is presented. The majority of programs emphasize either the meteorological aspects of the mixed layer or plume characterization. Few programs are available that provide the complimentary blend of plume and appropriate meteorological measurements needed to adequately validate mixed layer diffusion theory. Three major U.S. EPA (Environmental Protection Agency) field programs that provide data bases for model development and validation of mixed layer diffusion processes are described and discussed in more detail. The Regional Air Pollution Study (RAPS) focused on measurements of surface and mixed layer turbulent transport processes in the urban environment. The Tennessee Plume Study (TPS) obtained a database with coincident measurement of boundary layer turbulent structure and plume dispersion ...
1983-01-01
Energy Technology Data Exchange (ETDEWEB)
Coal can be converted to liquid fuels via three generically defined technologies: pyrolysis, direct hydroliquefaction, and indirect liquefaction. This paper presents a general overview of the indirect liquefaction technology and a discussion of processes tht are commercially available as well as those in the development stage. Finally, the objective of the DOE research and development program in conversion of synthesis gas derived from coal to transportation fuels is summarized. The current outlook for indirect liquefaction is encouraging. New facilities are being built in South Africe and New Zealand, and commercial plants could be designed and built for operation in the United States using proven technology. At the same time, developments in gasification as well as liquefaction catalysts and reactor technology promise significant improvements in indirect liquefaction processes in the years to come.
1982-01-01
Energy Technology Data Exchange (ETDEWEB)
Within the framework of efforts to optimize state-of-the-art waste disposal methods, this research project makes a theoretical analysis of the propagation behaviour of pollutants from landfills and waste incineration plants into the immediate vicinity of such plants. In order to judge the propagation of pollutants near the above-mentioned waste disposal facilities, a calculation program was developed within the framework of this research project which permits simulation of the propagation of such emissions in a three-dimensional space by application of an Eulerian grid model. It is capable of realistically representing fluid flow conditions and pollutant concentrations for certain points of times within the complex building patterns of such plants, for randomly chosen atmospheric conditions. (orig.)
1992-01-01
Safety analysis of FFTF loss of flow without scram tests
International Nuclear Information System (INIS)
A program of tests were conducted in July 1986 at the Fast Flux Test Facility (FFTF) to demonstrate that the reactor could withstand a prototypic loss of flow (LOF) without scram without sustaining fuel damage. The reactor was taken to powers up to 50%, and the main primary coolant pump motors were tripped without scramming the control rods. This paper summarizes the analyses performed to demonstrate the maintenance of redundant protection for all design events as well as potential new events introduced by the test. The analyses focused on the following consequences: (1) unexpected test behavior; (2) transient overpower event during the test; and (3) LOF event during the test.
1987-06-07
Radioactive waste management in the USSR: A review of unclassified sources. Volume 2
Energy Technology Data Exchange (ETDEWEB)
The Soviet Union does not currently have an overall radioactive waste management program or national laws that define objectives, procedures, and standards, although such a law is being developed, according to the Soviets. Occupational health and safety does not appear to receive major attention as it does in Western nations. In addition, construction practices that would be considered marginal in Western facilities show up in Soviet nuclear power and waste management operations. The issues involved with radioactive waste management and environmental restoration are being investigated at several large Soviet institutes; however, there is little apparent interdisciplinary integration between them, or interaction with the USSR Academy of Sciences. It is expected that a consensus on technical solutions will be achieved, but it may be slow in coming, especially for final disposal of high-level radioactive wastes and environmental restoration of ...
1991-03-01
Radioactive waste management in the USSR: A review of unclassified sources
Energy Technology Data Exchange (ETDEWEB)
The Soviet Union does not currently have an overall radioactive waste management program or national laws that define objectives, procedures, and standards, although such a law is being developed, according to the Soviets. Occupational health and safety does not appear to receive major attention as it does in Western nations. In addition, construction practices that would be considered marginal in Western facilities show up in Soviet nuclear power and waste management operations. The issues involved with radioactive waste management and environmental restoration are being investigated at several large Soviet institutes; however, there is little apparent interdisciplinary integration between them, or interaction with the USSR Academy of Sciences. It is expected that a consensus on technical solutions will be achieved, but it may be slow in coming, especially for final disposal of high-level radioactive wastes and environmental restoration of ...
1991-03-01
Pre-test report on international round robin analysis of BARC containment (BARCOM) test model
International Nuclear Information System (INIS)
BARC has organized an international round robin analysis program to carry out the ultimate load capacity assessment of BARC containment (BARCOM) test model. The test model located in BARC facilities Tarapur, is a 1:4 scale representation of 540 MWe pressurized heavy water reactor (PHWR) pre-stressed concrete inner containment structure of Tarapur Atomic Power Station (TAPS) unit 3 and 4. The features of the BARCOM test model and the constitutive data for the pre-test analysis along with the comparison of the results submitted by various participants are described in this pre-test report of the round robin analysis of BARCOM test model
2009-01-01
Energy Technology Data Exchange (ETDEWEB)
Since August 1984, the MITRE Corporation has been supporting the Naval Sea Systems Command (NAVSEA) and the Naval Medical Command (NAVMEDCOM) in their joint efforts to enhance the Navy Occupational Health Information Management System (NOHIMS). The goal of the enhancement effort was to create a comprehensive occupational health and safety system for Navy industrial facilities by expanding upon the original NOHIMS functions and adding modules for hazard deficiency abatement, hazardous-material control, injury claims and compensation, and safety and health training. To meet this goal, MITRE developed an enhanced industrial subsystem, referred to as the Occupational Safety and Health Record Keeping System (OSHRKS), using a prototyping approach and a public-domain data base-management software package, the Veterans Administration's (VA's) FileManager (FileMan).
1987-06-01
FFTF operating experience, 1982-1984
International Nuclear Information System (INIS)
The Fast Flux Test Facility (FFTF) is a 400 Mwt sodium-cooled fast reactor operating at the Hanford Engineering Development Laboratory, Richland, Washington, to conduct fuels and materials testing in support of the US Liquid Metal Fast Breeder Reactor (LMFBR) program. Startup and initial power testing included a comprehensive series of nonnuclear and nuclear tests to verify the thermal, hydraulic, and neutronic characteristics of the plant. A specially designed series of natural circulation tests were then performed to demonstrate the inherent safety features of the plant. Early in 1982, the FFTF began its first 100-day irradiation cycle. Since that time the plant has operated very well, achieving a cycle capacity factor of 94% in the most recent irradiation cycle. Seventy-five specific test assemblies and 25,000 individual fuel pins have been irradiated, some in excess of 80 MWd/Kg.
1984-04-09
Evolutionary developments advancing the floating production, storage, and offloading concept
Energy Technology Data Exchange (ETDEWEB)
Tanker-based floating production, storage and offloading (FPSO) systems have been in operation since Aug. 1977, when a single-well FPSO was put into production by Shell Espana in the Mediterranean. The overall operational experience with this system at this field is reviewed. Special attention is directed to the wireline workover facilities which have proven to be satisfactory. A subsequent evolutionary step, a FPSO accommodating multiple wells, necessitated development of a multiple-bore product swivel. A design program for this swivel was initiated in 1978, a prototype was built and fullscale testing finalized in 1980. A summary of the test results is presented. Simultaneous with the multiple-bore swivel development, detailed engineering for an 8-well FPSO was begun. This sytem includes gas lift a
1982-01-01
Evaluation of codisposal viability of MOX (FFTF) DOE-owned fuel: Phase 1 -- Intact mode calculations
Energy Technology Data Exchange (ETDEWEB)
The authors provide the intact criticality information that supports the disposal of spent nuclear fuel (SNF) from the US Department of Energy's (DOE's) Fast Flux Test Facility (FFTF) in the potential Monitored Geologic Repository at Yucca Mountain. FFTF is one of more than 250 forms of DOE-owned SNF. Because of the variety of the DOE SNF, the National Spent Nuclear Fuel Program has designated nine representative fuel groups for disposal criticality analyses based on fuel matrix, primary fissile isotope, and enrichment. The FFTF fuel is representative of the mixed-oxide fuel (MOX) group.
1999-07-01
Energy savings opportunity survey. US Army Field Station Kunia, Oahu, Hawaii. Final report
This Energy Savings Opportunity Survey (ESOS) is to identify Energy Conservation Opportunities (ECO`s) which are practical and economical for the reduction of energy consumption in accordance with the Army Facilities Energy Plan. The work to be performed under this project includes: (A) Coordinating with the on-going and proposed related projects. (B) Conducting a limited site survey required to identify applicable ECO`s and obtaining necessary data to evaluate the ECO`s. (C) Evaluating applicable ECO`s to determine their feasibility in accordance with current criteria. (D) Preparing programming and implementation documents for the recommended ECO`s. and (E) Preparing a comprehensive report to present the work performed including energy analysis, the results, and recommendations.
1989-06-01
Dual-fuel engine conversions evaluated by U.S. Navy
Energy Technology Data Exchange (ETDEWEB)
In seeking ways to reduce emissions from two-stroke locomotive type engines, the Navy has evaluated dual-fuel conversions operating on a compression ignition cycle, using up to 94% natural gas and 6% diesel pilot fuel. The Navy has conducted an evaluation and test program under the direction of Dr. Normnn L. Helgeson, at the Naval Facilities Engineering Service Center in Port Hueneme, California. Of the Navy`s many diesel engines, those installed in its MUSE (mobile utility support equipment) units for temporary electrical power were the first Navy off-road engines to be affected by emissions regulations. Most of the units are powered by the EMD 645 engine, and when burning diesel fuel do not meet the emission requirements in many areas of the country. This paper discusses the changes and results of the conversion and shakedown tests.
1996-10-01
Coal-liquefaction-process research. Quarterly report, April 1-June 30, 1982
This quarterly report, for the period April 1-June 30, 1982, summarizes Sandia's activities in coal liquefaction process research. The overall objectives of the program are to understand the mechanisms and determine the role of catalysts in the direct conversion of coal to liquids. Primary emphasis is being given to the Integrated Two-Stage Liquefaction (ITSL) process. Specific tasks include: short-contact time coal liquefaction, mineral matter effects and catalyst studies. During this period, work was done on: the characteristics of a Liquefaction (ITSL) facility at New Brunswick, NJ; the kinetics of hydrogenation and dehydrogenation of pyrene and dihydropyrenes in batch microreactors; the impact of coal cleaning on the effectiveness of two types of slurry phase catalysts; the deactivation of aged catalyst samples obtained from the H-Coal PDU; and a catalyst deactivation model for the H-Coal PDU.
1982-11-01
Energy Technology Data Exchange (ETDEWEB)
The International Atomic Energy Agency (IAEA) plans to use the Common Criteria, as the tool for developing graded and measurable evaluation criteria for information technology (IT) in safeguards systems in facilities subject to IAEA inspection. In their draft paper [ITSECSES] the IAEA defines a three-tiered Vulnerability Assessment Level (VAL) scheme. Each increased VAL level (1-3) defines additional and more stringent security and security-related requirements for the system developer, the system evaluator (assessor or authenticator), and for the IAEA. When all parties meet all requirements for a particular VAL level, IAEA has a measurable degree of confidence in the secure and proper operation of an IT system.
2001-12-06
Comparative study of computational model for pipe whip analysis
International Nuclear Information System (INIS)
Many types of pipe whip restraints are installed to protect the structural components from the anticipated pipe whip phenomena of high energy lines in nuclear power plants. It is necessary to investigate these phenomena accurately in order to evaluate the acceptability of the pipe whip restraint design. Various research programs have been conducted in many countries to develop analytical methods and to verify the validity of the methods. In this study, various calculational models in ANSYS code and in ADLPIPE code, the general purpose finite element computer programs, were used to simulate the postulated pipe whips to obtain impact loads and the calculated results were compared with the specific experimental results from the sample pipe whip test for the U-shaped pipe whip restraints. Some calculational models, having the spring element between the pipe whip restraint and the pipe line, give reasonably good transient ...
1993-08-15
Annual report 1988-89: Tata Institute of Fundamental Research
International Nuclear Information System (INIS)
The annual report surveys the work of the Tata Institute of Fundamental Research (TIFR), Bombay, during the fiscal year 1988-89. Most of the research activities are organised and carried out in two schools of the Institute, namely, the School of Mathematics and the School of Physics. In the School of Mathematics, active research is carried out in almost every branch of pure mathematics. The School of Physics is engaged in research activities of both theoretical and experimental nature in high energy physics, astrophysics, cosmic rays, space physics, astronomy, nuclear and atomic physics, condensed matter physics, molecular biology, computer science and communication and microwave engineering. TIFR has a Basic Dental Research Unit which carries out intervention studies on oral cancer and precancerous lesions. Its Homi Bhabha Centre for Science Education (HBCSE) carries out programmes for improvement of science education at all levels in the country. TIFR outstation ...
Physics through the 1990s: scientific interfaces and technological applications
Energy Technology Data Exchange (ETDEWEB)
The volume examines the scientific interfaces and technological applications of physics. Twelve areas are dealt with: biological physics--biophysics, the brain, and theoretical biology; the physics-chemistry interface--instrumentation, surfaces, neutron and synchrotron radiation, polymers, organic electronic materials; materials science; geophysics--tectonics, the atmosphere and oceans, planets, drilling and seismic exploration, and remote sensing; computational physics--complex systems and applications in basic research; mathematics--field theory and chaos; microelectronics--integrated circuits, miniaturization, future trends; optical information technologies--fiber optics and photonics; instrumentation; physics applications to energy needs and the environment; national security--devices, weapons, and arms control; medical physics--radiology, ultrasonics, NMR, and photonics. An executive summary and many chapters contain recommendations regarding funding, education, industry ...
1986-01-01
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 waste management system and problem-specific treatment approaches, waste form and treatment process adaptations, equipment ...
1988-09-01
Enhancement of science class in west central Alabama
Energy Technology Data Exchange (ETDEWEB)
Although the primary mission of the Southeastern Fish Culture Laboratory is to conduct scientific research on the problems facing the aquaculture industry, other goals are technology transfer and education. Over the past two years, a successful educational outreach program has been established with a local middle school. After a letter extending educational support to the public schools was written to the Superintendent, one teacher with her many science students began making monthly trips to the facility in order to gain hands-on experience in aquaculture science. The county supports the effort by providing the bus transport of thirty miles round trip. Students conduct a long-term experiment in fish growth while also learning about waterfowl, the environment, and the aquaculture industry. They are engaged in projects involving some hands-on experience. This program was judged to be successful doe to: (a) participant number ...
1994-12-31
Enhanced sludge washing evaluation plan
Energy Technology Data Exchange (ETDEWEB)
The Tank Waste Remediation System (TWRS) Program mission is to store, treat, and immobilize highly radioactive Hanford Site waste (current and future tank waste and the strontium/cesium capsules) in an environmentally sound, safe, and cost-effective manner. The scope of the TWRS Waste Pretreatment Program is to treat tank waste and separate that waste into HLW and LLW fractions and provide additional treatment as required to feed LLW and HLW immobilization facilities. Enhanced sludge washing was chosen as the baseline process for separating Hanford tank waste sludge. Section 1.0 briefly discusses the purpose of the evaluation plan and provides the background that led to the choice of enhanced sludge washing as the baseline process. Section 2.0 provides a brief summary of the evaluation plan details. Section 3.0 discusses, in some detail, the technical work planned to support the evaluation of enhanced sludge washing. ...
1994-09-01
Effectiveness of storage practices in mitigating aging degradation during reactor layup
Energy Technology Data Exchange (ETDEWEB)
One of the issues identified in the US Nuclear Regulatory Commission`s Nuclear Plant Aging Research program plan is the need to understand the state of ``mothballed`` or other out-of-service equipment to ensure subsequent safe operation. Programs for proper storage and preservation of materials and components are required by NRC regulations (10 CFR 50, Appendix B). However, materials and components have been seriously degraded due to improper storage, protection, or layup, at facilities under construction as well as those with operating licenses. Pacific Northwest Laboratory has evaluated management of aging for unstarted or mothballed nuclear power plants. The investigations revealed that no uniform guidance in the industry addresses reactor layup. In each case investigated, layup was not initiated in a timely manner, primarily because of schedule uncertainty. Hence, it is reasonable to assume that this delay resulted in ...
1995-09-01
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 from where they are generated to their ultimate disposal. This paper describes the development of the ANL Waste Minimization Plan and a pilot ...
1991-01-01
Energy Technology Data Exchange (ETDEWEB)
Concerns over the environment and energy security have recently prompted renewed interest in the U.S. in nuclear energy. Recognizing this, the U.S. Dept. of Energy has launched an initiative to revamp and modernize the role that modeling and simulation plays in the development and operation of nuclear facilities. This Nuclear Energy Advanced Modeling and Simulation (NEAMS) program represents a major investment in the development of new software, with one or more large multi-scale multi-physics capabilities in each of four technical areas associated with the nuclear fuel cycle, as well as additional supporting developments. In conjunction with this, we are designing a software architecture, computational environment, and component framework to integrate the NEAMS technical capabilities and make them more accessible to users. In this report of work very much in progress, we lay out the 'problem' we are addressing, describe the ...
2009-11-01
Commissioning and operation of BHP`s LCM plant
Energy Technology Data Exchange (ETDEWEB)
BHP Petroleum (BHPP) has now operated the 164 tonne per day Methanol Research Plant (MRP) located on the outskirts of Melbourne, Australia for over one year. This plant was commissioned in 1994 making first methanol on 17th October and has operated since then, selling product by pipeline to two local customers, ICI Adhesives and Borden Australia. The plant is based on the Leading Concept Methanol technology (LCM) licensed from ICI Katalco. Since 1985 BHPP has been involved in the development of Floating Production Storage and Offloading (FPSO) technology for the production of oil and gas offshore. In order to utilize the gas associated with oil on remote offshore oil production facilities the combination of gas conversion to methanol and existing FPSO technology is being investigated. The LCM technology being commercialized at the MRP is part of the strategy to demonstrate and develop LCM technology such that it could be located on the deck of a floating vessel in ...
1995-12-31
In October 1980, Air Products and Chemicals, Inc. began a three year contract with the DOE: Catalyst and Reactor Development for a Liquid Phase Fischer-Tropsch Process. The program contains four major tasks: (1) Project Work Plan, (2) Slurry Catalyst Development, (3) Slurry Reactor Design Studies, and (4) Pilot Facility Design. This report describes work on Tasks 2 and 3 carried out in the third quarter of the contract. In Task 2, the computerized search of the Fischer-Tropsch literature was continued, and improvements were made in data processing programs. Shakedown tests were completed on the first 300 ml slurry reactor, and construction of the second and third reactors began. Five modified conventional slurry catalysts were prepared, and two batches were tested in the gas phase giving information on selectivity as a function of composition and activation. Four supported cluster catalyst were synthesized, and seven were ...
1981-07-01
Workshop on NN Bremsstrahlung and Polarization Observables
The traveler participated in the discussions about the physics that can be learned in the experiments being planned, those presently running, or those recently completed by a growing number of major laboratories in Europe and the USA at the 'Workshop on NN Bremsstrahlung and Polarization Observables', where many representatives of these experimental programs were present. The traveler's research in this field is supported by a DOE Grant, and she has pioneered the early theoretical NN(lambda) treatments. In addition, she visited the Vrije University to collaborate with Professor Henk Blok on proton scattering from Zr-90 and neighboring nuclei. The traveler also visited NIKEF and discussed possible future experiments of mutual interest to be done at that laboratory.
1993-01-01
Vortex generator induced heat transfer augmentation past a rib in a heated duct air flow
Energy Technology Data Exchange (ETDEWEB)
The present investigation represents the initial phase of a comprehensive experimental program designed to study the potential for increasing the heat transfer per unit pressure drop in a ribbed duct by positioning vortex generators at key locations in the flow. In particular, the present investigation consists of a rib positioned at the inlet to a rectangular test section with uniform heating at its bottom wall. Local and average Nusselt number results are obtained for a circular rod positioned either immediately above or just downstream of the rib.
1992-02-01
Towards an understanding of the light scalar mesons
Energy Technology Data Exchange (ETDEWEB)
Although studied for many years the nature of the light scalar mesons remains controversial. Here we shall present a method, applicable for s-wave states located close to a threshold, that allows one to quantify the molecular part of a given state. When applied to the f{sub 0}(980) a dominance of the molecular component is found. In the second part, we show that requirements of field-theoretic consistency and chiral symmetry, when applied to the scattering of light pseudo-scalars, naturally lead to the appearance of dynamical poles in the scalar sector. A program is proposed on how to further investigate experimentally the mixing between these dynamical states and possible genuine quark states. (orig.)
2007-03-15
International Nuclear Information System (INIS)
In FY 1984 three specific tasks which are all related to not-well-understood two-phase phenomena of importance to LWR accidents have been identified under the program. These three tasks are: (1) inverted annular flow experiments and modeling; (2) hot leg U-bend two-phase flow simulation study; and (3) development and evaluation of two-phase flow scaling criteria. Some of the important results obtained under Tasks (1) and (2) are reported in this paper.
1984-10-23
On problems in trustworthy predictions of etched track parameters
Energy Technology Data Exchange (ETDEWEB)
It is discussed here how trustworthy predictions of etched track parameters in nuclear track detection technique can be made? Problems involved in doing so are described along with discussion about their possible solutions. Arguments are presented using 5.2 MeV alpha particle track etching experiments with CR-39 detector and corresponding calculations using computer programs TRACK{sub V}ISION and TRACK{sub T}EST. Experimental and computational results in the present paper are useful for further basic research and technology applications of solid state nuclear track detection technique.
2008-10-15
Formation and decay of secondary actinides in water reactor and fast neutron reactors
International Nuclear Information System (INIS)
Actinides other than the main uranium or plutonium isotopes take a growing part in the different stages of the nuclear cycle. For the French nuclear power program based on the development of light water reactors and fast breeders, many evaluations of the secondary actinides build up are made for the both reactor types using mainly the existing reactor codes. The comparison of these foreseen compositions with experimental results allows to perform some adjustments of the neutronic data. The secondary actinide compositions are given for some typical fuels and their consequences on the nuclear cycle are discussed. An hypothetical burning of these wastes in fast reactors has been studied and the main conclusions are reported.
Fluidic controls for the NERVA engine. Fourth semiannual progress report, November 1969--April 1970
International Nuclear Information System (INIS)
Development progress of the full-flow engine fluidic control system is reported. The fluidic temperature control subsystem was transferred from IR and D status to the SNP-1 program contract 1 December 1969. Several new fluidic control concepts were explored either experimentally or analytically. Basic component and subsystem design data at simulated engine state-point conditions were secured. Component design effort during the next six months will include fabrication and simulated tests of selected ''breadboard'' configurations. (auth).
Behavior of the cooling towers as a function of the time
International Nuclear Information System (INIS)
In the scope of the nuclear plants lifetime study, the behavior of the cooling towers is discussed. The main geometrical characteristics of the cooling towers in the French nuclear power plants, are presented. The surveyance program, the risks of accident, the research and development actions are considered. The results of the investigations of the cooling tower structure show that it is a multidiciplinary problem and needs the development of experimental and theoretical methods. Concerning the regenerators, the surveyance actions under operating conditions, the accelerated aging tests, and some aspects of the mechanical resistance, are underlined. It is shown that mainly the creep tests will allow the lifetime estimation of the materials developed for the regenerators.
1988-12-01
Technical data analysis program. Final report. [Fort Lewis and P-99; data consolidation
Separate comprehensive final reports on the status of the SRC-II Demonstration Plant Design and on operating experiences at the Ft. Lewis and P-99 SRC pilot plants were prepared after the termination of those projects. However, time constraints made it impossible to consolidate all of the pilot plant data and operating experiences and relate these to the Demonstration Plant or future plant design. Most of the experimental programs during the later stages of pilot plant operation were in direct support of specific technical uncertainties identified in design work. The results of these programs would have been of substantial use in verifying or modifying design philosophy had the project proceeded. This technical data analysis project was undertaken to consolidate the pilot plant results presented in numerous reports under DOE Contract DE-AC01-79ET10104 for operation of the pilot plants, and to relate these results to ...
1984-11-01
Structural analysis of experimental carbide fueled driver assmbly flow duct for testing in the FFTF
International Nuclear Information System (INIS)
Mixed carbide fueled driver assembly experiments will be tested in FFTF fuel driver positions as part of the National Advanced Fuel Program. The design of the experiment flow ducts must assure conformance to FFTF functional requirements in addition to service as a test vehicle for the carbide fuel irradiations. Test goals of damage fluence burnup, and fluence to burnup ratio exceed those of the standard oxide fueled drivers. As a consequence, the 20% cold worked type 316 stainless steel material of construction will experience significant irradiation induced creep and swelling. Additionally, the flow duct design must withstand the enhanced thermal transients produced by the action of carbide fuel during reactor scrams. A major FFTF functional requirement is that adjacent flow ducts do not touch each other except at the load pads. This requires a realistic analysis of the creep and swelling deformation of the flow duct during an experiment lifetime. Flow duct ...
Solid oxide fuel cell simulation and design optimization with numerical adjoint techniques
This dissertation reports on the application of numerical optimization techniques as applied to fuel cell simulation and design. Due to the "multi-physics" inherent in a fuel cell, which results in a highly coupled and non-linear behavior, an experimental program to analyze and improve the performance of fuel cells is extremely difficult. This program applies new optimization techniques with computational methods from the field of aerospace engineering to the fuel cell design problem. After an overview of fuel cell history, importance, and classification, a mathematical model of solid oxide fuel cells (SOFC) is presented. The governing equations are discretized and solved with computational fluid dynamics (CFD) techniques including unstructured meshes, non-linear solution methods, numerical derivatives with complex variables, and sensitivity analysis with adjoint methods. Following the validation of the fuel cell model in ...
2008-01-01
Geothermal Heat Pump research and development studies at Sandia National Laboratories
Energy Technology Data Exchange (ETDEWEB)
The Geothermal Heat Pump (GHP) concept was originally developed in the 1940`s. Recently, because of increasing energy costs, utility interest, and the development of simple and durable ground source heat exchangers, GHP`s have gained international attention as a proven means of energy conservation and electrical peak power demand reduction. GHP systems require installation of a buried heat exchanger to utilize the nearly constant ground temperature making them more efficient than conventional air source heat pumps. However, the high installation cost for both residential and commercial applications is a major obstacle to their market penetration. Sandia National Laboratories (SNL) through its sponsors, the Department of Energy (DOE), and the Department of Defense (DOD), has embarked on a research program to find ways to reduce GHP installation costs and improve performance, thereby increasing their market penetration. The major elements of the ...
1994-08-01
FIBROUS MONOLITH WEAR RESISTANT COMPONENTS FOR THE MINING INDUSTRY
Energy Technology Data Exchange (ETDEWEB)
A set of materials property data for potential wear resistant materials was collected. These materials are designated for use as the ''core'' materials in the Fibrous Monolith structure. The material properties of hardness, toughness, thermal conductivity and cost were selected as determining factors for material choice. Data for these four properties were normalized, and weighting factors were assigned for each property to establish priority and evaluate the effects of priority fluctuation. Materials were then given a score based on the normalized parameters and weighting values. Using the initial estimates for parameter priority, the highest ranking material was tungsten carbide, with diamond as the second ranked material. Several materials were included in the trade study, and five were selected as promising ''core'' materials to include in this effort. These materials are tungsten carbide, diamond, boron ...
2001-08-15
Energy Technology Data Exchange (ETDEWEB)
This paper describes the methods and systems as utilized in an integrated experimental thermohydraulic/mechanics analysis test program on waterhammer pressure pulses within a revised feedwater sparger of a Loviisa generation VVER-440-type reactor. This program was carried out in two stages: (1) measurements with a strictly limited set of operating parameters at Loviisa NPP, and (2) measurements with the full set of operating parameters on a test article simulating the revised feedwater sparger. The experiments at Loviisa NPS served as an invaluable source of information on the nature of waterhammer pressure pulses and structural responses. These tests thus helped to set the objectives and formulate the concept for series of tests on a test article to study the water hammer phenomena. The heavily instrumented full size test article of a steam generator feedwater sparger was placed within a pressure vessel simulating the ...
1997-12-31
Using benchmarking to minimize common DOE waste streams: Volume 5. Office paper waste
Energy Technology Data Exchange (ETDEWEB)
Finding innovative ways to reduce waste streams generated at US Department of Energy (DOE) sites by 50% by the year 2000 is a challenge for DOE`s waste minimization efforts. A team composed of members from several DOE facilities used the quality tool known as benchmarking to improve waste minimization efforts. First the team examined office waste generation and handling processes at their sites. Then team members developed telephone and written questionnaires to help identify potential ``best-in-class`` industry partners willing to share information about their best waste minimization techniques and technologies. The team identified two benchmarking partners, NIKE, Inc., in Beaverton, Oregon, and Microsoft, Inc., in Redmond, Washington. Both companies have proactive, employee-driven environmental issues programs. Both companies report strong employee involvement, management commitment, and readily available markets for recyclable materials such ...
1995-10-01
Savannah River Site production reactor safety analysis report. K production reactor
International Nuclear Information System (INIS)
Nuclear facilities of the Department of Energy (DOE) located at the Savannah River Site must comply with DOE orders as implemented at DOE-SR. The DOE orders cover safety criteria, design criteria, environmental protection, occupational health and safety. The program applies to DOE and contractors. In this section, the Nuclear Regulatory Commission (NRC) criteria and industry codes and standards are addressed as well as DOE orders. Specific DOE orders which add additional criteria have also been noted. A program for assessing and implementing contractor applicable DOE orders has been established. This program ensures that compliance is achieved through developing and implementing policies, programs, and procedures. The primary emphasis is placed on safe, efficient reactor restart and operation. DOE has classified orders applicable to restart as Level I, Category I while those ...
Energy Technology Data Exchange (ETDEWEB)
PETROBRAS/TRANSPETRO Pipelines and Terminals has 500 regular employees and 5.064 out sourced workers in its Southeast Division. The out sourced employees work through 125 contracts involving a wide range of activities such as maintenance, operational, pipeline launching , engineering, administrative and auxiliary services. Among these workers, 200 people are subjected to benzene occupational exposure, which might be present in the products we transport in our pipelines. Benzene is recognized as a carcinogen according to ACGIH and Brazilian Ministry of Labour regulation NR- 15. Exposure to benzene in an uncontrolled way, be it chronic or sharp, may affect the worker's health such as: hematological alterations, neoplasys, neurobehavior alterations. Our program PPEOB (acronym in Portuguese for benzene occupational exposure prevention program) involved the work force and fosters health by anticipation, recognition, evaluation and control ...
2004-07-01
International Nuclear Information System (INIS)
A series of 27 reflood experiments has been carried out in a full-length electrically heated rod bundle facility. The primary objective of these tests was to study the effects of a simultaneous upper plenum and downcomer coolant injection and to provide data for the verification of computer codes. The experimental results indicate that an upper plenum injection alone cools the test rods slowly, a simultaneous coolant injection to the downcomer improves cooling significantly, and a downcomer injection alone cools the test rod bundle best if the total value of the coolant flow rate is the same in these three different cases. If the coolant injected to the upper plenum increases the total flow rate, the quench time of the test rods decreases at all elevations. Quenching time and clad temperature histories calculated with the computer codes NORCOOL-I and FLOOD4 are in a reasonable quantitative agreement with experiments in the case of pure ...
1983-02-01
G3 model of gas and liquid migration from grout containing radioactive waste
Energy Technology Data Exchange (ETDEWEB)
Grout has been evaluated as a means of containing low-level radioactive waste for long-term disposal. Concerns about hydrogen and reactive gas generation in the Hanford Site grout disposal facility lead to the development of the G3 model, which has predicted buildup of radiolytically formed gases in the grout region and their migration to air-filled regions. The G3 model is a one-dimensional code that couples models of gas diffusion with two-phase gas and liquid flow. It was coupled to a compartment diffusion model and these models predicted the concentrations of hydrogen I nitrous oxide, and other gases in air-filled regions of the grout disposal facility. The results have served as the technical basis for safety studies. A unique finding of the G3 model was that a liquid return, or expulsion of unbound liquid from the grout region, could occur. This liquid return is driven by displacement caused by gas bubbles that form within the grout`s ...
1994-11-01
Fast Flux Test Facility reactor initial criticality predictions and measurements
International Nuclear Information System (INIS)
The Fast Flux Test Facility (FFTF) was designed to test fast-reactor fuels and other nonfuel materials. In its 37 reactor cycles of operations, the FFTF reactor has performed very well and successfully completed all the irradiation testings with an operating efficiency factor as high as 98%. Since FFTF is an experimental reactor, its core loading changed from cycle to cycle. Depending on the number of test assemblies in the core and their location, the core loading can change significantly from an essentially homogeneous core loading to a relatively nonhomogeneous or even highly localized heterogeneous loading. Consequently, the core reload design and initial criticality analyses were required for each operating cycle. The zero power initial critical control rod bank height was predicted before each reactor startup. The initial critical prediction depends on the reactivity conditions at the end of the previous cycle, the temperature feedback ...
1992-06-07
Energy Technology Data Exchange (ETDEWEB)
A numerical model of multiphase air-water flow and contaminant transport in the unsaturated zone is presented. The multiphase flow equations are solved using the two-pressure, mixed form of the equations with a modified Picard linearization of the equations and a finite element spatial approximation. A volatile contaminant is assumed to be transported in either phase, or in both phases simultaneously. The contaminant partitions between phases with an equilibrium distribution given by Henry`s Law or via kinetic mass transfer. The transport equations are solved using a Galerkin finite element method with reduced integration to lump the resultant matrices. The numerical model is applied to published experimental studies to examine the behavior of the air phase and associated contaminant movement under water infiltration. The model is also used to evaluate a hypothetical design for a low-level radioactive waste disposal facility. The model has been ...
1995-05-01
Energy Technology Data Exchange (ETDEWEB)
Some diagnostics at the National Ignition Facility (NIF), including the Gamma Reaction History (GRH) diagnostic, require multiple channels of data to achieve the required dynamic range. These channels need to be stitched together into a single time series, and they may have non-uniform and redundant time samples. We chose to apply the popular cubic smoothing spline technique to our stitching problem because we needed a general non-parametric method. We adapted one of the algorithms in the literature, by Hutchinson and deHoog, to our needs. The modified algorithm and the resulting code perform a cubic smoothing spline fit to multiple data channels with redundant time samples and missing data points. The data channels can have different, time-varying, zero-mean white noise characteristics. The method we employ automatically determines an optimal smoothing level by minimizing the Generalized Cross Validation (GCV) score. In order to automatically validate the ...
2010-12-28
International Nuclear Information System (INIS)
Full text of publication follows: As the coolant experiences no phase change in the core, SCWRs, unlike LWRs, cannot use design criteria based on the critical heat flux concept. The commonly accepted practice in SCWRs is to specify cladding temperature limits that must be met during transient and accident events. Therefore for the design of the SCWR, it is very important to predict the heat transfer coefficient to the supercritical water coolant with great accuracy. Our recent study focuses on the critical issue of measuring heat transfer to supercritical water at prototypical SCWR conditions and to develop the tools to predict the SCWR thermal behavior. A heat transfer test loop using a surrogate fluids, CO_2, is under construction. The reason of using CO_2 instead of water is that (i) valuable insight of the physical phenomena can be obtained with this fluid, and (ii) some existing facilities already used surrogate fluids, which in general have lower critical ...
2005-10-02
(Fast neutron cross section measurements)
Energy Technology Data Exchange (ETDEWEB)
In the 14 MeV Neutron Laboratory, we have continued the development of a facility that is now the only one of its kind in operation in the United States. We have refined the klystron bunching system described in last year's report to the point that 1.2 nanosecond pulses have been directly measured. We have tested the pulse shape discrimination capability of our primary NE 213 neutron detector. We have converted the RF sweeper section of the beamline to a frequency of 1 MHz to replace the function of the high voltage pulser described in last year's report which proved to be difficult to maintain and unreliable in its operation. We have also overcome several other significant experimental difficulties, including a major problem with a vacuum leak in the main accelerator column. We have completed additional testing to prove the remainder of the generation and measurement systems, but overcoming some of these ...
1991-01-01
UNSAT-H Version 3.0: Unsaturated Soil Water and Heat Flow Model Theory, User Manual, and Examples
Energy Technology Data Exchange (ETDEWEB)
The UNSAT-H model was developed at Pacific Northwest National Laboratory (PNNL) to assess the water dynamics of arid sites and, in particular, estimate recharge fluxes for scenarios pertinent to waste disposal facilities. During the last 4 years, the UNSAT-H model received support from the Immobilized Waste Program (IWP) of the Hanford Site's River Protection Project. This program is designing and assessing the performance of on-site disposal facilities to receive radioactive wastes that are currently stored in single- and double-shell tanks at the Hanford Site (LMHC 1999). The IWP is interested in estimates of recharge rates for current conditions and long-term scenarios involving the vadose zone disposal of tank wastes. Simulation modeling with UNSAT-H is one of the methods being used to provide those estimates (e.g., Rockhold et al. 1995; Fayer et al. 1999). To achieve the above goals for ...
2000-06-12
The US Advanced Liquid Metal Reactor and the Fast Flux Test Facility Phase IIA passive safety tests
International Nuclear Information System (INIS)
This report discusses the safety approach of the Advanced Liquid Metal reactor program, sponsored by the US Department of Energy, which relies upon passive reactor responses to off-normal condition to limit power and temperature excursions to levels that allow safety margins. Gas expansion modules (GEM) have included in the design to provide negative reactivity to enhance these margins in the extremely unlikely event that pumping power is lost and the highly reliable scram system fails to operate. The feasibility and beneficial features of these devices were first demonstrated in the core of the Fast Flux Test Facility (FFTF) in 1986. Preapplication safety evaluations by the US Nuclear Regulatory Commission have identified areas that must be addressed if these devices are to be relied on. One of these areas is the response of the reactor when it is critical and the pumps are turned on, resulting in positive reactivity being added to the core. ...
1992-10-25
International Nuclear Information System (INIS)
The safety approach of the Advanced Liquid Metal Reactor program, sponsored by the U.S. Department of Energy, relies upon passive reactor responses to off-normal conditions to limit power and temperature excursions to levels that allow large safety margins. Gas expansion modules (GEM) have been included in the design to provide negative reactivity to enhance these margins in the extremely unlikely event that pumping power is lost and the highly reliable scram system fails to operate. The feasibility and beneficial features of these devices were first demonstrated in the core of the Fast Flux Test Facility (FFTF) in 1986. Pre-application safety evaluations by the U.S. Nuclear Regulatory Commission have identified areas that must be addressed if these devices are to be relied on. One of these areas is the response of the reactor when it is critical and the pumps are turned on, resulting in positive reactivity being added to the core. Tests to ...
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 TWRS privatization strategy is a proof-of-concept/commercial ...
1996-11-01
A.C.R.O. activity report 2001; A.C.R.O. rapport d'activite 2001
Energy Technology Data Exchange (ETDEWEB)
As regards the environmental protection, the A.C.R.O. maintained in 2001 its programs of surveillance around the main western nuclear installations of France. The radioecological surveillance of the site of Cogema La-Hague for the dismantling of the former pipe of release in sea was one of the key points of this action environmental surveillance. The two accidents of atmospheric release in may and october 2001 at Cogema La Hague have shown the interest of an association as A.C.R.O.. It is thank to the measure, by our laboratory, of repercussions on environment of these incidents that it has been possible to bring to light a dysfunction of the measurement system of the gaseous effluents released by the facility operator. To improve the public information, A.C.R.O. concerns its main efforts on the development of the consumer technical information available on-line via its web site and in its regular publication 'the nuclear ...
2001-07-01
International Nuclear Information System (INIS)
The software package VIBA-lab1, which incorporates PIXE and RBS energy spectra simulation has now been extended to include the simulation of elemental maps from 3D structures. VIBA-lab1 allows the user to define a wide variety of experimental parameters, e.g. energy and species of incident ions, excitation and detection geometry, etc. When the relevant experimental parameters as well as target composition are defined, the program can then simulate the corresponding PIXE and RBS spectra. VIBA-LAB2 has been written with applications in nuclear microscopy in mind. A set of drag-and-drop tools has been incorporated to allow the user to define a three-dimensional sample object of mixed elemental composition. PIXE energy spectra simulations are then carried out on pixel-by-pixel basis and the corresponding intensity distributions or elemental maps can be computed. Several simulated intensity distributions for some 3D objects are ...
1999-09-02
PSDE/SAT-2: Communication system architecture study, executive summary
The PSDE/SAT-2 multimission satellite designed to offer a flight opportunity to different experimental communication payloads and verify the feasibility of advanced space technologies is described. It was conceived for expriment in the framework of the European DRS (Data Relay Satellite) program thus providing intersatellite and interorbit communication links, but also experimental and preoperative services. Payloads include optical communication single access payload (LSA); S-Band single access payload; S-Band multiple access payload; land mobile experimental payload; navigation payload; 40/50 GHz communication payload; and millimeter wave propagation payload. The orbital slot and interference analysis identified a limited number of orbital positions for the mission interleaved between Eutelsat satellites (i.e., 14 deg 30 min E and 17 deg 30 min E). A coordination is required in Ku-Band with Eutelsat ...
1988-01-01
Energy Technology Data Exchange (ETDEWEB)
A multi-faceted research program has been performed to investigate in detail several aspects of free and forced convective cooling of underground electric cable systems. There were two main areas of investigation. The first one, reported in Volume 1, dealt with the fluid dynamic and thermal aspects of various components of the cable system. In particular, friction factors for laminar flow in the cable pipes with various configurations were determined using a finite element technique; the temperature distributions and heat transfer in splices were examined using a combined analytical numerical technique; the pressure drop and heat transfer characteristics of cable pipes in the transitional and turbulent flow regime were determined experimentally in a model study; and full-scale model experimental work was carried out to determine the fluid dynamic and thermal characteristics of entrance and exit chambers for the cooling oil. ...
1981-05-01
Energy Technology Data Exchange (ETDEWEB)
A multi-faceted research program has been performed to investigate in detail several aspects of free and forced convective cooling of underground electric cable systems. There were two main areas of investigation. The first one reported in this volume dealt with the fluid dynamic and thermal aspects of various components of the cable system. In particular, friction factors for laminar flow in the cable pipes with various configurations were determined using a finite element technique; the temperature distributions and heat transfer in splices were examined using a combined analytical numerical technique; the pressure drop and heat transfer characteristics of cable pipes in the transitional and turbulent flow regime were determined experimentally in a model study; and full-scale model experimental work was carried out to determine the fluid dynamic and thermal characteristics of entrance and exit chambers for the cooling ...
1981-05-01
Experimental studies of pipe whip and impact: Final report
Energy Technology Data Exchange (ETDEWEB)
An experimental and computational study was undertaken to estimate the effects of pipe rupture and induced pipe whip impact on surround structures considered either as rigid or deformative such as concrete slabs. This program included sixteen tests using 3 inch schedule 80 (or 10) pipes made of carbon steel similar to A106 grade B. The study consisted of tests on rigid target and on concrete slab. The investigation of whip phase and impact phase was done separately for each test. For pipe impact on rigid targets, the impact forces are found to be directly related to the crush strength of the pipe and the general pipe deformation following the impact. For pipe impact on concrete slabs, the response of the target to the pipe impact needs to take into account the local effect such as penetration and localized damage on the slab. The test matrix covered a broad range of geometric parameters. It provides a significant data base for studying pipe ...
1987-02-01
Assessment of RELAP5 model for the University of Massachusetts Lowell research reactor
International Nuclear Information System (INIS)
RELAP5 (Reactor Excursion and Leak Analysis Program) is a system code developed at the Idaho National Environmental and Engineering Laboratory for thermal hydraulic analysis of nuclear reactors. The code RELAP5 is widely used for safety analysis studies of commercial nuclear power plants. However, recent released version of RELAP5/3.2 and over present significant capabilities for analysis of nuclear reactor research systems. As a contribution to the assessment of RELAP5/3.3 for research reactor safety analysis, experimental data from the University of Massachusetts Lowell Research Reactor UMLRR are used. The UMLRR is a 1 MW, light water moderated and cooled, graphite-reflected, open-pool type research reactor. This paper presents the development and the validation of a UMLRR-RELAP model using experimental data. For this purpose, a series of experiments were performed for benchmarking RELAP5 calculations for research reactor ...
Biological and Chemical Security
The LLNL Chemical & Biological National Security Program (CBNP) provides science, technology and integrated systems for chemical and biological security. Our approach is to develop and field advanced strategies that dramatically improve the nation's capabilities to prevent, prepare for, detect, and respond to terrorist use of chemical or biological weapons. Recent events show the importance of civilian defense against terrorism. The 1995 nerve gas attack in Tokyo's subway served to catalyze and focus the early LLNL program on civilian counter terrorism. In the same year, LLNL began CBNP using Laboratory-Directed R&D investments and a focus on biodetection. The Nunn-Lugar-Domenici Defense Against Weapons of Mass Destruction Act, passed in 1996, initiated a number of U.S. nonproliferation and counter-terrorism programs including the DOE (now NNSA) Chemical and Biological Nonproliferation ...
2002-12-19
Neutron cross-sections on minor actinides for next generation reactors: new data from n_TOF (CERN)
International Nuclear Information System (INIS)
Full text: Climatic problems associated to the greenhouse effect have recently stimulated a renewed interest in nuclear energy production, and triggered new studies aimed at developing future generation systems that would address current major safety, proliferation and waste concerns. In particular a possible solution to the waste problem could come from transmutation of the highly radiotoxic nuclear waste in Accelerator Driven Systems or in Generation-IV fast nuclear reactors. The design and operation of the new systems require accurate cross-section data on a large number of isotopes, in particular plutonium, minor actinides, long-lived fission fragments and structural materials. An important contribution to the field is being provided since a few years by a new time of-flight facility operative at CERN, n_TOF. The main features of the neutron beam, in particular the wide energy spectrum, ranging from thermal energy to hundreds of MeV, the very high instantaneous ...
2008-06-01
Application of the porous media model for the LWR process components
Energy Technology Data Exchange (ETDEWEB)
Full text of publication follows: A porous media solution PORFLO has been developed for the 3-dimensional two-phase flow by describing the process facility in Cartesian or cylindrical coordinates. The local porosity fraction is applied for distinguishing the fluid filled volumes from the solid structures. The solid structure contribute the two-phase flow through the wall friction, flow area and heat transfer. Optionally the solid structure may contain primary liquid of steam generators, steam in the higher temperature and pressure to be condensed or electrical heating power. By using these optional boundary conditions three different process facilities have been analysed. The thermohydraulic solution based on 5-equation approach, where the conservation equations are solved for the liquid and gas (vapour) mass, mixture momentum (giving the velocity only for the mixture), liquid and gas energy, is described shortly. In addition to that the ...
2005-07-01
Prior to 1978, the Wilsonville Advanced Coal Liquefaction facility material balance surrounded only the thermal liquefaction unit and involved analyses of only the slurry stream and individual gas streams. The distillate solvent yield was determined by difference. Subsequently, several modifications and additional process units were introduced to this single unit system. With the inclusion of the deashing unit in 1978 and the catalytic hydrogenation unit in 1981, the process has evolved into a sophisticated two-stage coal liquefaction process and has the potential for various modes of integration. This report presents an elemental balancing procedure and a simplified presentation format that is sufficiently flexible to meet current and future needs. The development of the elemental balancing technique and the relevant computer programs to handle the calculations have been addressed. This will be useful in modelling individual unit performance ...
1984-09-01
Target area chamber system design for the National Ignition Facility
International Nuclear Information System (INIS)
The National Ignition Facility (NIF) is a proposed Department of Energy facility which will contribute to the resolution of important Defense Program and inertial fusion energy issues for energy production in the future. The NIF will consist of a laser system with 192 independent beamlets transported to a target chamber. The target chamber is a multi-purpose structure that provides the interface between the target and the laser optics. The chamber must be capable of achieving moderate vacuum levels in reasonable times; it must remain dimensionally stable within micron tolerances, provide support for the optics, diagnostics, and target positioner; it must minimize the debris from the x-ray and laser light environments; and it must be capable of supporting external neutron shielding. The chamber must also be fabricated from a low neutron activation material. The fusion reaction in the target gives off neutrons, x-ray and ...
1994-06-19
Resolving issues at the Department of Energy/Oak Ridge Operations Facilities
Energy Technology Data Exchange (ETDEWEB)
Waste management, like many other issues, has experienced major milestones. In 1971, the Calvert Cliff's decision resulted in an entirely different approach to the consideration of environmental impact analysis in reactor siting. The accidents at Three Mile Island and Chernobyl have had profound effects on nuclear power plant design. The high-level waste repository program has had many similar experiences that have modified the course of events. The management of radioactive, hazardous chemical and mixed waste in all of the facilities of the Oak Ridge Operations (ORO) Office of the Department of Energy (DOE) took on an entirely different meaning in 1984. On April 13, 1984, Federal Judge Robert Taylor said that DOE should proceed 'with all deliberate speed' to bring the Y-12 plant into compliance with the Resource Conservation and Recovery Act and the Clean Water Act. This decision resulted from a suit brought by the ...
1988-01-01
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. The case study looks into several past and ...
2003-02-24
Isotope Production at the Hanford Site in Richland, Washington
Energy Technology Data Exchange (ETDEWEB)
This report was prepared in response to a request from the Nuclear Energy Research Advisory Committee (NERAC) subcommittee on ''Long-Term Isotope Research and Production Plans.'' The NERAC subcommittee has asked for a reply to a number of questions regarding (1) ''How well does the Department of Energy (DOE) infrastructure sme the need for commercial and medical isotopes?'' and (2) ''What should be the long-term role of the federal government in providing commercial and medical isotopes?' Our report addresses the questions raised by the NERAC subcommittee, and especially the 10 issues that were raised under the first of the above questions (see Appendix). These issues are related to the isotope products offered by the DOE Isotope Production Sites, the capabilities and condition of the facilities used to produce these products, the management of the isotope production ...
1999-06-01
Energy Technology Data Exchange (ETDEWEB)
A Lurgi baseline study was requested by the DOE/GRI Operating Committee of the Joint Coal Gasification Program for the purpose of updating the economics of earlier Lurgi coal gasification plant studies for the production of substitute natural gas (SNG) based on commercially advanced technologies. The current study incorporates the recent experience with large size Lurgi plants in an effort to improve capital and operating costs of earlier plant designs. The present coal gasification study is based on a mine mouth plant producing 250 billion Btu (HHV) per day of SNG using the Lurgi dry bottom coal gasification technology. A Western subbituminous coal was designated as the plant food, obtained from the Rosebud seam at Colstrip, Montana. This study presents the detailed description of an integrated facility which utilizes coal, air, and water to produce 250 billion Btu (HHV) per day of SNG. The plant consists of coal handling and preparation, ...
1984-09-01
Total cross sections of ultracold neutron interactions with some gases
Energy Technology Data Exchange (ETDEWEB)
Measurement results of total interaction cross sections averaged by the spectrum of ultracold neutrons (UCN) within the rate range from 3.2 to 5.7 m/s at the temperatures of 80 and 300 K for the following gases: hydrogen, parahydrogen, helium-4, nitrogen, neon, argon, xenon are presented. The experiment has been conducted conducted in the facility for UCN extraction, mounted in the radial channel of the WWR-K reactor. Experimental dependences of UCN counting rate on pressure of the investigated gases in the chamber varying from 0 to 1.5x10/sup 3/ torr are presented graphically. The measured total cross sections mainly satisfactorily agree with calculations, divergences are observed only for hydrogen and xenon.
1981-11-01
Energy Technology Data Exchange (ETDEWEB)
The ability of the /sup 252/Cf-source-driven neutron noise analysis method to measure subcriticality has been demonstrated in a variety of experimental configurations of fissile materials. Calculations for an approximately 4-m-dia configuration of light water reactor (LWR) fuel elements indicated the feasibility of measuring the subcriticality of large, loosely coupled arrays of LWR fuel elements by this same method. These analysis suggested application to the initial loading of both pressurized and boiling water reactors, zero-power testing of reactors (such as shutdown margin measurements after initial loading), light water reactor refueling, and safe storage of LWR spent fuel. In the fuel storage application, direct measurement of subcriticality in the actual fuel storage facilities provides the parameter which is directly related to criticality safety.
1984-01-01
Performance of hydrous titanium oxide-supported catalysts in coal-liquids upgrading
Experimental tests were performed in a continuous-flow hydrotreating unit at Pittsburgh Energy Technology Center to evaluate the performance of hydrous titanium-oxide supported (HTO) catalysts as hydrotreating catalysts for use in two-stage coal liquiefaction. Catalysts containing either a combination of CO, Ni, and Mo as the active metal components or Pd as the active metal componet were tested with representative hydrotreater feed stocks from the Wilsonville Advanced Coal Liquefaction Research and Development Facility. Catalyst performance evaluation was based on desulfurization and denitrogenation activity, the conversion of cyclohexane-insolbule material, and hydrogenation activity during 100-hour reactor runs. Results indicated that the HTO catalysts were comparable to a commercial Ni/Mo-alumina supported catalyst in the areas evaluated. 11 refs., 1 fig., 6 tabs.
1988-01-01
Nuclear Charge Radius of Lithium-11
Energy Technology Data Exchange (ETDEWEB)
We have determined the nuclear charge radius of 11Li by high-precision laser spectroscopy. The experiment was performed at the TRIUMF-ISAC facility where the 7Li-11Li isotope shift was measured in the 2s to 3s electronic transition using Doppler-free two-photon spectroscopy with a relative accuracy better than 10 5. The accuracy reached in previous experiments on the other lithium isotopes was improved. Most of the isotope shifts measured in the experiment are due to difference in the mass of the nuclei but small contributions are produced by the change in proton distribution, QED and relativistic effects have to be taken into account as well. By comparing the experimental results with sophisticated atomic calculations of the mass dependent effect the nuclear charge radii of the lithium isotopes are found to decrease monotonically from 6Li to 9Li while the nuclear charge radius of 11Li is about 11% larger than that of 9Li.
2006-07-01
Modelling of two-phase natural circulation in a WWER-plant: PMK experimental results
International Nuclear Information System (INIS)
Experiments have been performed with the PMK integral-type facility, a model of WWER-440 type PWRs, to investigate two-phase natural circulation behaviour. The phenomena to be expected in this reactor type are different from those in PWRs with vertical steam generators mainly due to the loop seal in the hot leg and the horizontal layout of the steam generator heat transfer tubes. The experiments showed that the system is repressurized when the water level drops to the hot leg elevation due to the effect of the loop seal. Opening of the loop seal can be smooth, but may lead to oscillations depending on the power and the mass inventory. Natural circulation recovers after the hot leg loop seal is opened, but then decreases with further mass inventory decrease. (orig.).
British Library Electronic Table of Contents (United Kingdom)
The total photoabsorption cross section on a free proton was measured at the GRAAL facility in the energy range E ? = 600?1500 MeV. The large-aperture LAGRAN?E detector and a liquid hydrogen target were used in the experiment performed with a back-scattered Compton gamma beam. To improve the accuracy, two alternative methods were employed. First, a subtraction method of using empty-target measurements allowed the cross section ? tot to be evaluated directly because of a low level of the electromagnetic background. Second, an algorithm for evaluating ? tot on the basis of summing the dominating partial cross sections was developed. Experimental results obtained for ? tot by the two methods are compared with existing data.
2008-01-01
Index structures for structured documents
Energy Technology Data Exchange (ETDEWEB)
Much research has been carried out in order to manage structured documents such as SGML documents and to provide powerful query facilities which exploit document structures as well as document contents. In order to perform structure queries efficiently in a structured document management system, an index structure which supports fast document element access must be provided. However, there has been little research on the index structures for structured documents. In this paper, we propose various kinds of new inverted indexing schemes and signature file schemes for efficient structure query processing. We evaluate the storage requirements and disk access time of our schemes and present the analytical and experimental results.
1996-12-31
How to organize a neutron imaging user lab? 13 years of experience at PSI, CH
British Library Electronic Table of Contents (United Kingdom)
PSI has a relatively long tradition in neutron imaging since the first trials were done at its formerly existing research reactor SAPHIR with film methods. This reactor source was replaced after its shutdown in 1994 by the spallation neutron source SINQ in 1996, driven by the 590MeV cyclotron for protons with presently up to 2.3mA beam current. One of the first experimental devices at SINQ was the thermal neutron imaging facility NEUTRA, which was designed from scratch and has been the first device of its kind at a spallation source. Until now, NEUTRA has been successfully in use for many investigations in a wide range of studies covering fuel cell research, environmental behavior of plants, nuclear fuel inspection and the research on cultural heritage objects. It has been the host of PhD ...
2011-01-01
British Library Electronic Table of Contents (United Kingdom)
To analyze the effect of containment spray on gas mixing and depressurization, two experiments (ST3_1 and ST3_2) were performed with two interconnected vessels. These experiments were conducted in the frame of the OECD/SETH-2 project using the PANDA facility. The vessels were preconditioned such that a helium-rich layer is formed in the upper section of the first vessel, henceforth referred to as Vessel-1. In the case of the first experiment (ST3_1), the remaining volume of Vessel-1 and the entirety of the second vessel, Vessel-2, were filled with pure steam. For ST3_2, the second experiment presented here, pure steam was replaced with a steam-air mixture instead. Water was injected from the top of Vessel-1 with a spray nozzle projecting downwards. Transient behavior of system pressure, as...
2011-01-01
Energy Technology Data Exchange (ETDEWEB)
This report is to present the progress made on the project ''Establishment of an Environmental Control Technology Laboratory (ECTL) with a Circulating Fluidized-Bed Combustion (CFBC) System'' during the period October 1, 2004 through December 31, 2004. The following tasks have been completed. First, the renovation of the new Combustion Laboratory and the construction of the Circulating Fluidized-Bed (CFB) Combustor Building have proceeded well. Second, the detailed design of supporting and hanging structures for the CFBC was completed. Third, the laboratory-scale simulated fluidized-bed facility was modified after completing a series of pretests. The two problems identified during the pretest were solved. Fourth, the carbonization of chicken waste and coal was investigated in a tube furnace and a Thermogravimetric Analyzer (TGA). The experimental results from this study are presented in this report. Finally, ...
2005-01-30
Acid mine water treatment in wetlands: an overview of an emergent technology
Energy Technology Data Exchange (ETDEWEB)
Experimental wetlands are being constructed on mined lands in the United States as an inexpensive alternative to conventional acid mine water treatment facilities. The US Bureau of Mines is conducting an inventory of these constructed wetlands as part of a long-term evaluative study. Preliminary results, based on the 20 sites surveyed to date, indicate that the wetlands dominated by emergent species are out-performing the Sphagnum-dominated wetlands, and that much of the water treatment is accomplished by other aspects of the wetland, including bacteria, algae, amendments and other plants. Iron concentrations as high as 85 mg/l are reduced to less than 3 mg/l after flow through the constructed wetlands. Manganese is also removed, though somewhat less efficiently. 12 refs., 1 fig., 1 tab.
1987-12-31
DARPA Program Composition for Embedded Systems (PCES) ...
... Title : DARPA Program Composition for Embedded Systems (PCES) Program Capstone Demonstration Video (Postprint) (CD-ROM). ...
2005-09-01
Geothermal Technologies Program: News
and Renewable Energy EERE Home | Programs & Offices | Consumer Information Geothermal Technologies Program Search Search Help Geothermal Technologies Program HOME ABOUT...
2011-08-21
EERE: Geothermal Technologies Program Home Page
and Renewable Energy EERE Home | Programs & Offices | Consumer Information Geothermal Technologies Program Search Search Help Geothermal Technologies Program HOME ABOUT...
2011-08-21
Energy Technology Data Exchange (ETDEWEB)
The presentation summarises the highlights of experimental results obtained for VVER type horizontal steam generator heat transfer, primary side flow pattern, and mixing in the hot collector during secondary side boil-off with primary at single-phase natural circulation. The experiments were performed using the PACTEL facility with Large Diameter (LD) steam generator models, with collector instrumentation designed specifically for these tests. The key findings are as follows: (1) the primary to secondary heat transfer degrades as the secondary water inventory is depleted, following closely the wetted tube area; (2) a circulatory flow pattern exists in the tube bundle, resulting in reversed flow (from cold to the hot collector) in the lower part of the tube bundle, and continuous flow through the upper part, including the tubes that have already dried out; and (3) mixing of the hot leg flow entering the hot collector and reversed, cold, tube ...
1997-12-31
Evaluation of Core Bypass Flow in the Prismatic VHTR with a Multi-block Experiment
International Nuclear Information System (INIS)
The core of Prismatic Modular Reactor (PMR) consists of assemblies of hexagonal graphite fuel and reflector elements. The core bypass flow of Very High Temperature Reactor (VHTR) is defined as the core flow that does not pass through the coolant channels but passes through the bypass gap between fuel elements. The increase in bypass flow makes the decrease in effective coolant flow. Since the core bypass flow has a negative impact on safety and efficiency of VHTR, core bypass phenomena have to be investigated to improve the core thermal margin of VHTR. For this purpose, the international project, I-NERI project, has been carried out since 2008. I-NERI project is collaborative project that KAERI and SNU of Korea side and INL, ANL and TAMU of U.S side are involved. In order to evaluate the core bypass flow, the multicolumn and multi-layer experimental facility is designed by SNU. In this experiment, the effect of cross-flow and local variation of ...
2010-10-01
Development of pyro-separation technology based on molten salt electrolysis
International Nuclear Information System (INIS)
In order to effectively recover uranium, rotation speed of solid cathode was examined, and effect of uranium concentration and current density on electrodeposition were confirmed. And the potentiostatic and galvanostatic electrorefining experiments were conducted. Element used in the experiments were Zr, Nd, La chlorides. The reduction potentials of chlorides metals on liquid Cd cathode were measured by cyclic voltammetry experiments. The electrowinning experiments were performed in order to recover small amounts of uranium in salt. Experimental set-up for the batch type reductive extraction experiments were developed and installed. On the base of experimental results of batch type, multi-stage extraction equipment was set-up, and optimum number of stage and recover yield were measured. In the oxidative extraction study is examine selective separation behavior of the rare earth metals from alloy composed of actinide and lanthanide metals to ...
2010-10-01
International Nuclear Information System (INIS)
There has been recent interest in the United States concerning the loss of residual heat removal system (RHRS) under reduced coolant inventory conditions for pressurized water reactors. This issue is also of interest in the Federal Republic of Germany and an experiment was performed in the integral PKL-III experimental facility at Siemens-KWU to supply applicable data. Recently, an NRC-sponsored effort has been undertaken at the Idaho National Engineering Laboratory to identify and analyze the important thermal-hydraulic phenomena in pressurized water reactors following the long term loss-of-RHRS during reduced inventory operation. The thermal-hydraulic response of a closed reactor coolant system during such a transient is investigated in this report. Some of the specific processes investigated include: reflux condensation in the steam generators, the corresponding pressure increase in the reactor coolant system, and void fraction distributions ...
1992-04-01
A reactor-neutrino experiment, Daya Bay, has been proposed to determine the least-known neutrino mixing angle theta_13 using electron antineutrinos produced at the Daya Bay nuclear power complex in China. Daya Bay is an international collaboration with institutions from China, the United States, the Czech Republic, Hong Kong, Russia, and Taiwan. The experiment will use eight identical detectors deployed at three different locations optimized for monitoring the antineutrino rates from the six reactors and for detecting any rate deficit and spectral distortion near the first oscillation maximum. The overburden of the under ground experimental halls, connected with tunnels, ranges from about 250 to 900 meters-water-equivalent so that the cosmogenic background is small compared to the number of observed antineutrino events. Civil construction of tunnels and experimental facilities is planned to start in 2007, with detector ...
2007-01-01
Indian Academy of Sciences (India)
central server with search facility involving all partner journals ...
Hyperspectral and Multispectral Remote Sensing at Uranium Processing Facilities
Energy Technology Data Exchange (ETDEWEB)
Many mines and processing facilities are in remote, difficult to access areas, or are in areas where access is limited or restricted for national reasons. In a joint project with Canada Centre for Remote Sensing, the Canadian Safeguards Support Program is investigating utility of multi- and hyperspectral remote sensing for remotely inspecting such site. With a view to eventually using the hyperspectral satellite data now coming available, airborne data over uranium and copper mine tailings and uranium processing facilities in northern Canada were acquired. The objective of this work is to demonstrate that multispectral and hyperspectral data can provide complementary and supplementary information to high-resolution panchromatic imagery for the following safeguards applications: Inspection aids (up-to-date maps of remote locations), change detection, evaluation of member state declarations, monitoring of reactor, mining and ...
2003-05-01
Experimental and theoretical studies on humidification-dehumidification-desalination
Energy Technology Data Exchange (ETDEWEB)
The shortage of fresh water is increasing at alarming levels, even in temperate zones. Desalination of brackish and seawater is being considered as a solution to growing water demands. Seawater desalination can be accomplished through reverse osmosis, vapor compression, vapor absorption and thermally driven systems. The most suitable process for large-scale desalination plants is successive brine evaporation-condensation with intermediate heat recovery. However, higher process efficiency could be achieved. The use of low temperature heat sources in seawater desalination requires an efficient method of evaporation and condensation at relatively low vapor pressures. This could be achieved in a humidification-dehumidification process using circulated air to enhance evaporation of water. Simulation models, however, neglect either the heat of evaporation or the changes in air and water properties within humidification and condensation towers. Therefore, the purpose of this study was to ...
2006-07-01
Energy Technology Data Exchange (ETDEWEB)
In its beginning, the U.S. Department of Energy (DOE) Office of Environmental Management (EM) viewed private industry as lacking adequate technology know-how to meet demands of hazardous and radioactive waste problems at the DOE`s laboratories and nuclear weapons production facilities. In November 1989, EM`s Office of Technology Development (recently renamed the Office of Science and Technology) embarked on a bold program of developing and demonstrating {open_quotes}innovative{close_quotes} waste cleanup technologies that would be safer, faster, more effective, and less expensive than the {open_quotes}baseline{close_quotes} commercial methods. This program has engaged DOE sites, national laboratories, and universities to produce preferred solutions to the problems of handling and treating DOE wastes. More recently, much of this work has shifted to joint efforts with private industry partners to accelerate the use of newly ...
1996-12-31
It`s slim with a plain green cover: Australia`s management plan for polychlorinated biphenyls
Energy Technology Data Exchange (ETDEWEB)
In November 1995, the Australian and New Zealand Environment and Conservation Council (ANZECC, the Council of State and National Environment Ministers) adopted a National Management Plan for PCBs. This was a significant milestone in the very long saga of Australian efforts to develop public policy and management structures for dealing with persistent organochlorine wastes. The author was part of a four-person consultation panel that carried out a public involvement program to assist and inform the process of developing the National Management Plan. The program involved, among other things, visiting every state and territory of Australia at least twice. This paper describes the development and delivery of the public involvement program, including ongoing interactions with Governments. The latter is often a complex (and many would say an unduly complex) matter in the federal system, where primary responsibility for waste ...
1996-12-31
High-pressure ceramic air heater for indirectly fired gas turbine applications
Energy Technology Data Exchange (ETDEWEB)
The Externally-Fired Combined Cycle (EFCC) offers a method for operating high-efficiency gas and steam turbine combined cycles on coal. In the EFCC, an air heater replaces the gas turbine combustor so that the turbine can be indirectly fired. Ceramic materials are required for the heat exchange surfaces to accommodate the operating temperatures of modern gas turbines. The ceramic air heater or heat exchanger is the focus of this program, and the two primary objectives are (1) to demonstrate that a ceramic air heater can be reliably pressurized to a level of 225 psia (1.5 MPa); and (2) to show that the air heater can withstand exposure to the products of coal combustion at elevated temperatures. By replacing the gas turbine combustor with a ceramic air heater, the cycle can use coal or other ash-bearing fuels. Numerous programs have attempted to fuel high efficiency gas turbines directly with coal, often resulting in significant ash deposition ...
1992-01-01
High-pressure ceramic air heater for indirectly fired gas turbine applications
Energy Technology Data Exchange (ETDEWEB)
The Externally-Fired Combined Cycle (EFCC) offers a method for operating high-efficiency gas and steam turbine combined cycles on coal. In the EFCC, an air heater replaces the gas turbine combustor so that the turbine can be indirectly fired. Ceramic materials are required for the heat exchange surfaces to accommodate the operating temperatures of modern gas turbines. The ceramic air heater or heat exchanger is the focus of this program, and the two primary objectives are (1) to demonstrate that a ceramic air heater can be reliably pressurized to a level of 225 psia (1.5 MPa); and (2) to show that the air heater can withstand exposure to the products of coal combustion at elevated temperatures. By replacing the gas turbine combustor with a ceramic air heater, the cycle can use coal or other ash-bearing fuels. Numerous programs have attempted to fuel high efficiency gas turbines directly with coal, often resulting in significant ash deposition ...
1992-12-01
Field-effect research at the High Voltage Transmission Research Center
Energy Technology Data Exchange (ETDEWEB)
This report presents information obtained during five different studies of field effects from high voltage transmission lines performed at EPRI's High Voltage Transmission Research Center. The first study is the development of a methodology for the evaluation of the expected frequency of occurrence of specific short-term effects of spark discharges and induced currents caused by overhead high voltage transmission lines. The methodology is divided into the analysis of the expected frequency of occurrence of situations in which induction effects may occur, and the analysis of the expected severity of the effect. The second study is of the electric field in the surface and on the immediate proximity of the strands of stranded conductors used for overhead high voltage lines. In particular, the cases of deformations of stranded conductors, caused by air expansion or by popped out strands, are analyzed for the purpose of determining the conditions for occurrence of corona in fair ...
1991-02-01
Study on core cooling of hybrid safety system for next-generation PWR during LOCA
International Nuclear Information System (INIS)
Mitsubishi is now developing a next-generation Pressurized Water Reactor (PWR) which has the innovative feature of hybrid safety systems (optimum combination of passive safety system and active safety system) and passive core cooling by horizontal steam generators during Loss of Coolant Accident (LOCA). In order to confirm the capability of this passive core cooling system during LOCAs, the thermal-hydraulic tests of horizontal steam generator and the integral thermal-hydraulic tests simulating the LOCAs were performed. The thermal-hydraulic tests of horizontal steam generator consist of a single tube test and a multi-tubes test. On the basis of these test results, the heat transfer characteristics of steam-water two-phase flow with noncondensable gas along a long horizontal tube is understood and the heat transfer correlation including the effect of noncondensable gas is presented. The integral thermal-hydraulic tests simulate the small LOCA and the large LOCA using the SLIM loop ...
1995-04-23
Energy Technology Data Exchange (ETDEWEB)
The effective fraction of delayed photoneutrons ({beta}{sup ph}) has been theoretically defined and experimentally determined in various different configurations of the LWR-PROTEUS critical facility. The peculiarity lies in the fact that the reactor has D{sub 2}O in only one of the four fuelled zones, thus D({gamma},n)H reactions take place mainly in this region. The work is divided into three parts. The first part is devoted to the description of the LWR-PROTEUS facility and to the measurements of {beta}{sup ph}. These experimental values are derived from standard inverse-kinetics analysis of neutron flux decay experiments for each of seven different configurations, with nine additional groups of neutron precursors to account for photoneutron effects. In the second part, the coupled neutron and gamma Boltzmann equations are reduced to exact point kinetics equations using the photon infinite-velocity ...
2003-11-01
Differential rod worth profile affected by axial blankets in FFTF [Fast Flux Test Facility
International Nuclear Information System (INIS)
The central feature of the Fast Flux Test Facility (FFTF) is the fast test reactor (FTR), which is a liquid-sodium-cooled fast reactor providing high fast-neutron flux for irradiation testing of fuels and materials. The FTR also provides a means to develop breeder reactor core components and to gain reactor systems operating experience for future liquid-metal fast breeder reactors (LMFBRs). In the FTR core, there are 82 incore positions (within rows 1 through 6) available for driver fuel assemblies and/or test assemblies. In addition, there are three safety rods and six control rods located in rows 3 and 5, respectively, in the three symmetric core sectors. The FFTF has been successfully and continuously operated for more than 11 reactor cycles. For the first 8 cycles, the core loadings were composed of the mixed-oxide driver fuel assemblies and some test assemblies. These assemblies have an active core section of 91.5 cm with 15.2-cm upper and lower reflectors. ...
1990-06-10
International Nuclear Information System (INIS)
The COSA II (computer codes for salt) benchmark problem has been pursued with the ADINA (Automatic Dynamic Incremental Nonlinear Analysis) program code. With the use of this, the code should be validated by means of experimental data and the ability to reproduce real-life calculation results of the KfK (Kernforschungszentrum Karlsruhe/Nuclear Research Center in Karlsruhe) should be proven. A successful validation of the code then forms the foundation stone for the ability to use different calculation problems in the final (ultimate) storage. This also accompanies the consequent reaction of replacing the STEALTH (Solids and Thermal Hydraulics Code for EPRI Adapted from LAGRANGE TOODY and HEMP) program which has a number of program-specific weaknesses compared to the ADINA computer code. In order to reproduce the approximate values from the KfK, the same values have been used. Differences were evident in ...
Performance Assessment Monitoring Plan for the Hanford Site Low-Level Burial Grounds
Energy Technology Data Exchange (ETDEWEB)
The U.S. Department of Energy Order 435.1, Radioactive Waste Management, requires a disposal authorization statement authorizing operation (or continued operation) for low-level waste disposal facilities. In fulfillment of these requirements, a disposal authorization statement was issued on October 25, 1999, authorizing the Hanford Site to transfer, receive, possess, and dispose of low-level radioactive waste at the 200 East Area burial grounds and the 200 West Area burial grounds. One of the conditions is that monitoring plans for the 200 East Area and 200 West Area low-level burial grounds be written and approved by the Richland Operations Office. As a result of a record of decision for the Hanford Site Solid Waste Program and acceptance of the Hanford Site Solid Waste Environmental Impact Statement, the use of the low-level burial ground (LLBG) as a disposal facility for low-level and mixed low-level wastes has been ...
2006-03-30
Status of he-cooled divertor development (PPCS subtask TW4-TRP-001-D2)
International Nuclear Information System (INIS)
Within the framework of the EU power plant conceptual study (PPCS), helium-cooled modular divertor concepts have been investigated in detail at the Forschungszentrum Karlsruhe during the past few years. The first conceptual design proposed was based on convective cooling with the use of flow promoters in the form of pin and/or slot arrays (HEMP/HEMS) to increase the cooling surface and, hence, enhance the heat transfer capacity. While continuing the design optimisation, an advanced multiple-jet design (HEMJ) was introduced, which is based on direct jet-to-wall impinging cooling and offers advantages in terms of simple construction and manufacturing. Main emphasis of the 2004 work program (TW4-TRP-001) lay on experiments for the concepts HEMJ and HEMS, which were mainly performed at the Efremov Institute in St. Petersburg, Russia. For experiment preparation, detailed test programs were worked out and accompanying CFD analyses were accomplished. ...
Energy Technology Data Exchange (ETDEWEB)
The purpose and need for DOE to undertake the actions described in this document are to improve the efficiency of the Alternating Gradient Synchrotron (AGS) complex. Benefits would include optimization of the AGS scientific program, increased high-energy and nuclear physics experimentation, improved health and safety conditions for workers and users, reduced impact on the environment and the general public, energy conservation, decreased generation of hazardous and radioactive wastes, and completion of actions required to permit the AGS to be the injector to the Relativistic Heavy Ion Collider (RHIC)., Improved efficiency is defined as increasing the AGS`s capabilities to capture and accelerate the proton intensity transferred to the AGS from the AGS booster. Improved capture of beam intensity would reduce the beam losses which equate to lost scientific opportunity for study and increased potential for radiation doses to workers and the general ...
1994-03-01
Energy Technology Data Exchange (ETDEWEB)
An experimental and analytical study was performed to improve understanding of the dynamic impact behavior of carbon steel pipes. The test program addressed two types of pipe impact scenarios using both 2- and 4-in. Sch-80 pipes and elbows. Projectile-on-pipe tests simulated the behavior of a stationary target pipe which is impacted at its center by a larger, more rigid whipping pipe. These target pipes, which contained non-flowing water at about 290{degree}C temperature and ca 8.5 megapascals pressure, exhibited a peak deformation of up to 45% reduction in their diameter. For each test condition, the local deformation at the impact zone is a function of the peak impact force and impact velocity. Pipe-on-wall tests simulated the impact of an elbow at the free end of a cantilevered whipping pipe with a rigid barrier. The peak crush of the impact zone of the elbows was a function of peak impact force. Numerical analyses of dynamic impact tests ...
1984-06-01
Oil shale today : thoughts on why the majors stay away
Energy Technology Data Exchange (ETDEWEB)
This article discussed potential reasons why most major oil companies are not currently investing in oil shale resources. At present, only Shell, Chevron-Texaco, and ExxonMobil are engaged in oil shale pilot schemes. It was suggested that one of the reasons oil companies are reluctant to become involved is due to weak responses to experimental leasing programs conducted by the federal government of the United States, which are not favourable for commercial-scale operations. A federally sponsored leasing program and clear unconventional resource energy policies are needed, and unconventional oil resources must be developed in order to prevent escalating oil prices. The economics of oil shale recovery are equivalent to those obtained by Alberta's oil sands operators. Large amounts of char and hydrogen in the oil shale add value. However, oil shale processing has significant environmental impacts. Major oil companies ...
2008-07-15
Modelling of temperature field in a reactor vessel downcomer during transients
International Nuclear Information System (INIS)
The B test series from the course of ISP Nr. 43 was analysed. The boundary conditions measured include the initial temperature of the primary system, the front/slug injection flowrate and temperature, and the pressure drop across the core. Temperature data were collected at 185 thermocouple positions in the downcomer and 38 positions in the lower plenum. The frequency of data acquisition for code predictions was set to 2 Hz, which corresponds to the acquisition frequency of the two experimental setups. Calculations were performed using the FLUENT Computational Fluid Dynamics (CFD) code. This program is based on the finite volume method, The computational mesh was generated by the pre-processor - GAMBIT program. FLUENT uses a control-volume-based technique to convert the governing equations to algebraic equations, which can be solved numerically. This control volume technique consists of integrating the governing equations ...
2003-08-17
Linearized augmented-plane-wave calculation of the electronic structure and total energy of tungsten
International Nuclear Information System (INIS)
Local-density-functional calculations of the energy bands, equilibrium lattice constant, bulk modulus, and cohesive energy have been performed using a newly developed self-consistent full-potential linearized augmented-plane-wave (LAPW) program. Scalar-relativistic effects are included for the band states, and the core-level states are treated fully relativistically in a central-field approximation. Excellent agreement is obtained with the experimental lattice constant and bulk modulus. Generally good agreement is obtained with the scalar-relativistic pseudopotential results of Bylander and Kleinman. In this context, the impact of various approximations used in including the core states is assessed, and these findings are related to the frozen-core and pseudopotential approximations, especially with regard to the treatment of the somewhat overlapping 5p semicore states and their effect on ground-state properties. Comparison with the recent LAPW ...
Graphite Technology Development Plan
Energy Technology Data Exchange (ETDEWEB)
This technology development plan is designed to provide a clear understanding of the research and development direction necessary for the qualification of nuclear grade graphite for use within the Next Generation Nuclear Plant (NGNP) reactor. The NGNP will be a helium gas cooled Very High Temperature Reactor (VHTR) with a large graphite core. Graphite physically contains the fuel and comprises the majority of the core volume. Considerable effort will be required to ensure that the graphite performance is not compromised during operation. Based upon the perceived requirements the major data needs are outlined and justified from the perspective of reactor design, reatcor performance, or the reactor safety case. The path forward for technology development can then be easily determined for each data need. How the data will be obtained and the inter-relationships between the experimental and modeling activities will define the technology development for graphite ...
2007-09-01
Energy Technology Data Exchange (ETDEWEB)
A program is currently in progress at Argonne National Laboratory to evaluate and develop evaporator technology for concentrating radioactive waste streams. By concentrating radioactive waste streams, disposal costs can be significantly reduced. To effectively reduce the volume of waste, the evaporator must achieve high decontamination factors so that the distillate is sufficiently free of radioactive material. One technology that shows a great deal of potential for this application is being developed by LICON, Inc. In this program, Argonne plans to apply LICON`s evaporator designs to the processing of radioactive solutions. Concepts that need to be incorporated into the design of the evaporator include, criticality safety, remote operation and maintenance, and materials of construction. To design an effective process for concentrating waste streams, both solubility and vapor-liquid equilibrium data are needed. The key issue, however, is the ...
1993-10-01
Digital libraries play a crucial role in distance learning. Nowadays, they are one of the fundamental information sources for the students enrolled in this learning system. These libraries contain huge amount of instructional data (text, audio and video) offered by the distance learning program. Organization of the digital libraries is therefore very important for easy and fast access to the desired information. Improper categorization of data may mislead the students searching the library. Since manual categorization of huge amount of data might be challenging, an automatic and reliable method is needed. In this sense, this paper proposes an automated categorization scheme for digital libraries in distance learning. The categorization scheme is designed and developed by a pattern recognition approach. Effectiveness of the proposed scheme is evaluated on widely used Reuters database. The results of the experimental study verify that ...
2008-10-01
Accelerated stability test techniques for middle distillate fuels
Energy Technology Data Exchange (ETDEWEB)
Improved test techniques are needed for evaluating the inherent stability of middle distillate fuels both in surveillance and in procurement activities. A project was initiated to define and evaluate the contributing conditions leading to the formation of deleterious products in accelerated aging tests of middle distillate fuels and to relate these results to an experimental definition of more repeatable/reliable middle distillate fuel stability test technique(s). A literature search was conducted to provide a list of stability test techniques and their interpretations which could be used in a correlative middle distillate fuel stability test program. For this program, seven accelerated stability tests were chosen and evaluated using a set of six test fuels. The test techniques were selected to represent a wide variety of test conditions, including temperature, aging time, and oxygen availability. These six test fuels were ...
1981-01-01
Environmental Sciences Division annual progress report for period ending September 30, 1981
Energy Technology Data Exchange (ETDEWEB)
Research programs from the following sections and programs are summarized: aquatic ecology, environmental resources, earth sciences, terrestrial ecology, advanced fossil energy program, toxic substances program, environmental impacts program, biomass, low-level waste research and development program, US DOE low-level waste management program, and waste isolation program.
1982-04-01
Coal Liquefaction Program: Fiscal year 1989, Summary program plan
Energy Technology Data Exchange (ETDEWEB)
Program plans of the Office of Coal Technology in coal liquefaction are presented. Technology description, status, market applications, program strategy and program management descriptions are included. 2 figs. (CBS)
1989-01-01
Energy Technology Data Exchange (ETDEWEB)
The Integrated Status and Effectiveness Monitoring Program (ISEMP - BPA project No.2003-0017) has been created as a cost effective means of developing protocols and new technologies, novel indicators, sample designs, analytical, data management and communication tools and skills, and restoration experiments that support the development of a region-wide Research, Monitoring and Evaluation (RME) program to assess the status of anadromous salmonid populations, their tributary habitat and restoration and management actions. The most straightforward approach to developing a regional-scale monitoring and evaluation program would be to increase standardization among status and trend monitoring programs. However, the diversity of species and their habitat, as well as the overwhelming uncertainty surrounding indicators, metrics, and data interpretation methods, requires the testing of multiple approaches. Thus, ...
2009-01-01
Tribopolymerization as an anti-wear mechanism. Progress report
Energy Technology Data Exchange (ETDEWEB)
During the first phase of this project, significant progress was made in several of the connected issues that make up the objectives of this grant. The central thrust or theme of this work under the DOE/ERIP grant is to carry out prototype testing of the concept of tribopolymerization as a novel mechanism of boundary lubrication--under more severe, high-load, high-speed conditions that are most likely to exist in field applications. The authors see this as an important step in attracting industries to license and market the results of this new technology. In addition, they have began to explore other potential, energy-saving applications of the concept of tribopolymerization. These exploratory studies are quite promising; they are likely to open new doors in industrial applications. To carry out the experimental part of this program, a new device has been built. Highlights of these and other developments are given.
1995-12-01
The propagation of relativistic heavy ions in multielement beam lines.
We describe calculations of the energy loss, range, stopping power, multiple scattering, and other related properties of a high-energy heavy-ion beam at any one of a set of beam line elements. A beam line element (e.g., any beam modification, detection, or control device) is characterized by its thickness, areal density, aperture, and function. The loss of multiply scattered particles to any finite-aperture detector is calculated in the small-angle approximation, and the position of the Bragg peak, as given by particles stopping in the second of two ionization chambers used for Bragg curve measurements, is estimated. A general purpose computer program, PROPAGATE, has been written to allow addition, deletion, and modification of the beam line elements used in the calculation and to provide a convenient means of repeating such calculations for arbitrary beam lines. Calculations and experimental measurements are compared and found to be in ...
The development of Soviet rocket engines (For strategic missiles)
Energy Technology Data Exchange (ETDEWEB)
A first-hand account of developments in the Soviet rocket industry is presented. The organization and leadership of the rocket and missile industry are traced from its beginning in the 1920s. The development of the Glushko Experimental Design Bureau, where the majority of Soviet rocket engines were created, is related. The evolution of Soviet rocket engines is traced in regard to both their technical improvement and their application in missiles and space vehicles. Improved Glushko engines and specialized Isaev and Kosberg engines are discussed. The difficulties faced by the Soviet missile and space program, such as the pre-Sputnik failures, the oscillation problem of 1965/1966, which exposed a weakness in Soviet ICBM missiles, and the Nedelin disaster of 1960, which cost the lives of more than 200 scientists and engineers, as well as the Commander-in-Chief of the Strategic Rocket Forces, Marshall Nedelin, are examined. 122 refs.
1991-01-01
British Library Electronic Table of Contents (United Kingdom)
This study emphasizes the need for a systematic and in-depth connection between the progress in quantum theory of energetic ion collisions and applications to hadron therapy. Scattering theory for fast ion beams has reached its stage of development where accurate and robustly applicable methodologies can advantageously be exported to applied fields such as space research, fusion energy program, medicine, etc. In particular, distorted wave collision theories at high energies readily provide total, partial and fully differential cross sections for inelastic collisions of ionic projectiles with any target system. By numerous and thorough testings, such theoretical cross sections were found to exhibit excellent agreement with experimental data on atomic targets. Adequate extensions of these me...
2010-01-01
International Nuclear Information System (INIS)
In this paper, a time-domain equivalent circuit method is applied to solve dispersion of coupled-cavity travelling-wave tube (CCTWT). First, the time-domain circuit equations of CCTWT coupled-cavity chain are deduced from the equivalent circuit model. Then, the equations are solved numerically by fourth-order Runge-Kutta method and a program CTTDCP is developed using MATLAB. Last, a L-band CCTWT is calculated using CTTDCP and the cavity pass-band of this tube is computed to be 1.08-1.48 GHz, which is consistent with the experimental results and the simulation results of electromagnetic code and demonstrates the validity of the time-domain equivalent circuit method. In addition, a new design method which uses the equivalent circuit method and electromagnetic simulation together to optimize the cold cavity characteristics of CCTWT is proposed. (authors)
2008-09-01
Progress on significant R and D projects
This report updates the status of 32 large projects having EPRI authorizations of $5 million or more. It also describes 86 smaller projects that have EPRI authorizations of less than $5 million and that have a high likelihood of producing a utility-useful new near-term accomplishment within the next two years. Finally, there are 45 examples of analytical, experimental and bench-scale projects that were influential in confirming or redirecting EPRI's research program. These examples cover the entire spectrum of electric R and D: (1) fuel processing, (2) electric power generation, (3) transmission and distribution, (4) energy storage and management, (5) energy analysis, and (6) environmental assessment and control.
1982-08-01
Phenomenology of light systems using R-matrix theory.
Energy Technology Data Exchange (ETDEWEB)
Over the last 30 years, a program of R-matrix analyses has been carried out at Los Alamos in the mass range 2 {le} A {le} 18 that gives useful information about the light systems. These analyses provide data for astrophysics, as well as for neutronic and thermonuclear applications, and can yield important constraints from the experimental measurements on the nature of few-body interactions. Following a brief introduction to R-matrix theory, I will describe recent work on reactions in the A=2 (NN) and A=4 systems. Finally, some comments will be made about extending the theory to complex energies in order to obtain information about resonances and other types of S-matrix singularities.
2001-01-01
Energy Technology Data Exchange (ETDEWEB)
This report describes progress during the first year of a three-year project. The objective of the research is to examine new design approaches for achieving very high conversion efficiencies. The program is divided into two areas. The first centers on exploring new thin-film approaches specifically designed for III-V semiconductors. The second area centers on exploring design approaches for achieving high conversion efficiencies without requiring extremely high quality material. Research activities consisted of an experimental study of minority carrier recombination in n-type, metal-organic chemical vapor deposition (MOCVD)-deposited GaAs, an assessment of the minority carrier lifetimes in n-GaAs grown by molecular beam epitaxy, and developing a high-efficiency cell fabrication process.
1993-01-01
New III-V cell design approaches for very high efficiency
Energy Technology Data Exchange (ETDEWEB)
This report describes progress during the first year of a three-year project. The objective of the research is to examine new design approaches for achieving very high conversion efficiencies. The program is divided into two areas. The first centers on exploring new thin-film approaches specifically designed for III-V semiconductors. The second area centers on exploring design approaches for achieving high conversion efficiencies without requiring extremely high quality material. Research activities consisted of an experimental study of minority carrier recombination in n-type, metal-organic chemical vapor deposition (MOCVD)-deposited GaAs, an assessment of the minority carrier lifetimes in n-GaAs grown by molecular beam epitaxy, and developing a high-efficiency cell fabrication process.
1993-01-01
Energy Technology Data Exchange (ETDEWEB)
Testing was initiated in March 1991 and completed in November 1992 to determine the rate at which asphalt is biodegraded by microorganisms native to the Hanford Site soils. The asphalt tested (AR-6000, US Oil, Tacoma, Washington) is to be used in the construction of a diffusion barrier for the Hanford grout vaults. Experiments to determine asphalt biodegradation rates were conducted using three separate test sets. These test sets were initiated in March 1991, January 1992, and June 1992 and ran for periods of 6 months, 11 months, and 6 months, respectively. The experimental method used was one originally developed by Bartha and Pramer (1965), and further refined by Bowerman et al. (1985), that determined the asphalt biodegradation rate through the measurement of carbon dioxide evolved.
1993-04-01
International Nuclear Information System (INIS)
Charge carrier profiles are measured for boron implanted into silicon (E = 30 keV, dose range 5 x 10"1"5 to 2 x 10"1"6 B/cm"2) after rapid isothermal annealing using halogen lamps. Maximum temperatures between 1000 and 1300 "0C and holding times at T/sub max/ of 5 and 20 s are used for the annealing treatment. In a few additional experiments flash lamp annealing at 1350 "0C (pulse duration 20 ms) is investigated. By comparison of the experimental profiles with computer simulations using the SUPREM II program transient enhanced diffusion of boron could be detected in all investigated cases. Maximum charge carrier concentrations above the equilibrium solubility of boron are observed and are discussed. (author).
Energy Technology Data Exchange (ETDEWEB)
Theoretical and experimental data which have defined and/or extended the effectiveness of remote sensing operations are explored, with consideration given to both scientific and commercial activities. The remote sensing of soil moisture, the sea surface, and oil slicks is discussed, as are programs using satellites for studying geodynamics and geodesy, currents and waves, and coastal zones. NASA, Canadian, and Japanese radar and microwave passive and active systems are described, together with algorithms and techniques for image processing and classification. The SAR-580 project is outlined, and attention is devoted to satellite applications in investigations of the structure of the atmosphere, agriculture and land use, and geology. Design and performance features of various optical scanner, radar, and multispectral data processing systems and procedures are detailed.
1982-01-01
International Nuclear Information System (INIS)
We have performed X-ray magnetic diffraction (XMD) experiment of ferromagnets at the Photon Factory (PF) of the High Energy Accelerator Research Organization (KEK) in Tsukuba. In this study, we have upgraded the XMD experimental system in order to apply this method to as many samples as possible. Upgrade was made for (1) the X-ray counting system and related measurement program, (2) the electromagnet, and (3) the refrigerator. The performance of the system was enhanced so that (1) the counting rate capability was improved from 104cps to 105cps, (2) the maximum magnetic field was increased from 0.85T to 2.15T, and (3) the lowest sample temperature was reduced from 15K to 5K. The new system was applied to an orbital ordering compound of YTiO3, and we obtained spin magnetic form factor for the reflection plane (010) perpendicular to the b axis. The magnetic field of 2T was needed to saturate the magnetization of YTiO3 along the b axis. These are ...
2007-01-19
Understanding of the volatility of GeO/sub 2/ in the presence of WO/sub 2/
Energy Technology Data Exchange (ETDEWEB)
The equilibria composition of the gaseous and the solid phase in the system GeO/sub 2//WO/sub 2/ is calculated with an improved thermodynamical program for temperatures 1100 < T < 1400 K and constant volume. By means of the results the experimental observed migration of GeO/sub 2/ in the presence of WO/sub 2/ in a temperature gradient T/sub 2/ ..-->.. T/sub 1/ (1200 ..-->.. 1100 K) in sealed evacuated silica tubes is due to a chemical transport with H/sub 2/ as the transporting agent. The H/sub 2/ is formed by H/sub 2/O which is desorbed by the quartz glass of the ampoules. The also observed volatility of WO/sub 2/ and its deposition in form of Ge/sub 0.75/W/sub 3/O/sub 9/ at the 'cold' end (T/sub 1/) of the tubes is performed by gaseous GeWO/sub 4/. The calculated and experimental transport rates are compared and discussed.
1983-08-01
Simulation of electromechanical and thermomechanical loads on first wall mock-ups
International Nuclear Information System (INIS)
In order to study the boundary conditions for the occurrence of ratcheting, a testing rig was erected. In this rig, small-scale mock-ups of the first wall were tested under mechanical conditions similar to those expected during disruptions. These mock-ups were made of stainless steel AISI 316. They were heated on the surface and water cooled from inside. Disruption forces were simulated by a high-speed hydraulic bending system by impact loads. The mock-ups were heated by a high-frequency generator and cooled by water through two cooling channels.In addition to the experimental work, simplified analytical analysis and numerical calculations were carried out using the finite element program ABAQUS. In these calculations, the temperature and stress fields in the mock-ups were investigated and the influence of the different constitutive equations was studied.The experimental results confirm the ratcheting behaviour predicted by ...
Energy Technology Data Exchange (ETDEWEB)
This two-volume proceedings summarize the results of fifteen innovations that were funded through the US Department of Energy`s Innovative Concept Program. The fifteen innovations were presented at the sixth Innovative Concepts Fair, held in Austin, Texas, on April 22--23, 1993. The concepts in this year`s fair address innovations that can substantially reduce or use waste streams. Each paper describes the need for the proposed concept, the concept being proposed, and the concept`s economics and market potential, key experimental results, and future development needs. The papers are divided into two volumes: Volume 1 addresses innovations for industrial solid waste processing and municipal waste reduction/recycling, and Volume 2 addresses industrial liquid waste processing and industrial gaseous waste processing. Individual reports are indexed separately.
1993-04-01
Mercury modeling for PWSCC length sizing. [Primary water stress corrosion cracking
This report describes the results of EPRI Program S404-28, titled Experimental Modeling of Eddy Current Response'', conducted by the Westinghouse Science and Technology Center (STC). The Westinghouse STC demonstrates that its mercury modeling technique provides an unique bridge between steam generator eddy current field inspection conditions and predictions obtained using recently developed analytical models. The mercury modeling technique was used systematically to explore factors which contribute to primary water stress corrosion cracking (PWSCC) sizing inaccuracy, including probe design, coil excitation frequency, crack length, and crack morphology. Two new proposed techniques for inverting crack lengths from eddy current data are compared with the technique commonly used in field data analysis for PWSCC. The performance of uniform field eddy current probes is compared with the performance of pancake coil probe designs, ...
1992-08-01
Mercury modeling for PWSCC length sizing. [Primary water stress corrosion cracking
Energy Technology Data Exchange (ETDEWEB)
This report describes the results of EPRI Program S404-28, titled Experimental Modeling of Eddy Current Response'', conducted by the Westinghouse Science and Technology Center (STC). The Westinghouse STC demonstrates that its mercury modeling technique provides an unique bridge between steam generator eddy current field inspection conditions and predictions obtained using recently developed analytical models. The mercury modeling technique was used systematically to explore factors which contribute to primary water stress corrosion cracking (PWSCC) sizing inaccuracy, including probe design, coil excitation frequency, crack length, and crack morphology. Two new proposed techniques for inverting crack lengths from eddy current data are compared with the technique commonly used in field data analysis for PWSCC. The performance of uniform field eddy current probes is compared with the performance of pancake coil probe designs, and ...
1992-08-01
Finite element analysis of pipe whip restraint behavior under jet thrust forces
International Nuclear Information System (INIS)
Many types of pipe whip restraints are installed to protect the structural components from the anticipated pipe whip phenomena of high energy lines in nuclear power plants. It is necessary to investigate these phenomena accurately in order to design the pipe whip restraints properly and/or to evaluate the acceptability of the pipe whip restraint design. Various research programs have been conducted in many countries to develop analytical methods and to verify the validity of the methods. In this study, various types of finite elements in ANSYS, the general purpose finite element computer grogram, was used to simulate the postulated pipe whips to obtain impact loads and the calculted results were compared with the specific experimental results from the sample pipe whip test for the U-chaped pipe whip restraints. Some calculational models, having the gap element or the spring element between the pipe whip restraint and the pipe line, give ...
Energy Technology Data Exchange (ETDEWEB)
Combustion scientists are primarily concerned with the fuels most often burned as energy sources (coal, petroleum products, and natural gas), with the goal of learning to burn them as efficiently, intensely, and cleanly as possible. Discovering those slight rearrangements of chemical bonds that together account for the net chemical transformation is the key to understanding how combustion proceeds. Once these reactions have been defined, the chemist can determine the rate coefficient of each reaction as a function of temperature and assemble the information into flame models. The computer programs that use these models to predict experimental results combine two sets of equations describing (1) the diffusive and reactive rates of change in concentration of all the molecules in the flame and (2) the flow of the reacting gases. Although the details of hydrocarbon-flame models are still disputed, many of their general features are clear and the ...
1982-02-01
Energy Technology Data Exchange (ETDEWEB)
In order to gain a wider knowledge of corrosion phenomena in OFHC (oxygen free high conductivity) copper pipes of the stator cooling circuit of a power plant turboalternator, a research program was laid out which is based on the use of an experimental loop simulating real operating conditions as closely as possible. The samples examined were either copper foils or hollow conductors of the type that is normally used in the stator cooling system, and the circulating fluid was high purity water with controlled O/sub 2/, H/sub 2/ and C0/sub 2/ contents. Investigations were focused on the kinetics of O/sub 2/ removal through catalytic resins covered with metallic palladium (at different temperatures and pressures) and on the kinetics of CO/sub 2/ removal through mixed bed resins. Subsequently, attention was directed to the corrosion of copper (in the form of foils or hollow conductors) under different experimental conditions ...
1991-12-31
Wind for Schools (Presentation)
Energy Technology Data Exchange (ETDEWEB)
Schools are key to achieving the goal of producing 20% of the nation's electricity demand. Most significantly, schools are training the scientists, technicians, businesspeople, decisionmakers, and teachers of the future. What students learn and believe about wind energy will impact the United States' ability to create markets and policy, develop and improve technology, finance and implement projects, and create change in all of our public and private institutions. In the nearer term, school districts have large facility costs, electrical loads, and utility costs. They are always in search of ways to reduce costs or obtain revenue to improve educational programs. Schools value teaching about the science and technology of renewable energy. They are important opinion leaders, particularly in rural communities. And their financial structures are quite different from other institutions (funding, incentives, restrictions, etc.). ...
2007-06-01
Slope stability and stabilization methods
Energy Technology Data Exchange (ETDEWEB)
Slope stability can be a major problem during the construction of surface facilities. Cutting into existing ground disturbs the mechanics of the surrounding area, which can result in landslides and rock falls. This practical reference gives you the comprehensive information you need for slope stability analysis, suitable methods of analysis with and without the use of computers, and examples of common stability problems and stabilization methods for cuts and fills. It includes detailed discussions of methods used in slope stability analysis, including the Ordinary Method of Slices, Simplified Janbu Method, Simplified Bishop Method, Spencer`s Method, other limit equilibrium methods, numerical methods, total stress analysis, effective stress analysis, and the use of computer programs to solve problems. Chapters include: General Slope Stability Concepts; Engineering Geology Principles; Groundwater Conditions; Geologic Site Exploration; Laboratory ...
1995-12-01
Sintered Reaction Bonded Silicon Parts by Microwave Nitridation Combined with Gas-Pressure Sintering
Energy Technology Data Exchange (ETDEWEB)
The cooperative project was a joint development program between Ceradyne and Oak Ridge National Laboratory through Lockheed Martin Energy Research (LMER). Cooperative work was of benefit to both parties. ORNL was able to assess the effect of the microwave nitridation process coupled with gas-pressure sintering for fabrication of parts for advanced diesel engines. Ceradyne gained access to gelcasting expertise and microwave facilities and experience for the nitridation of SRBSN materials. The broad objective of the CRADA between Ceradyne and OIWL was to (1) examine the applicability of the gelcasting technology to fabricate parts from SRBSN, and (2) to assess the effect of the microwave nitridation of silicon process coupled with gas-pressure sintering for fabrication of parts for advanced diesel engines. The following conclusions can be made from the work performed under the CRADA: (1) Gelcasting is a viable method to fabricate SRBSN parts ...
1999-01-01
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 and TRU waste disposal. Postponing the ...
1994-08-15
PANDA passive decay heat removal transient test results
International Nuclear Information System (INIS)
PANDA is a large scale facility for investigating the long-term decay heat removal from the containment of a next generation of 'passive' Advanced Light Water Reactors (ALWR). PANDA was used to examine the long-term LOCA response of the Passive Containment Cooling System (PCCS) for the General Electric (GE) Simplified Boiling Water Reactor (SBWR). The first PANDA test series had the dual objectives of demonstrating the performance of the SBWR PCCS and extending the data base available for containment analysis code qualification. The test objectives also include the study of the effects of mixing and stratification of steam and noncondensible gases in the drywell (DW) and in the suppression chamber or wetwell (WW). Ten tests were conducted in the course of the PANDA SBWR Program. The tests demonstrated a favorable and robust overall PCCS performance under different conditions. The present paper focuses on the main phenomena observed during the ...
Observational approach implementation guidance: Year-end report
Energy Technology Data Exchange (ETDEWEB)
It is generally recognized that the Remedial Investigation/Feasibility Study (RI/FS) process can be time-consuming and costly. To expedite the process, the Environmental Protection Agency, through the National Contingency Plan and Office of Solid Waste and Emergency Response (OSWER) Directives, has promoted streamlining'' the RI/FS. The concept of streamlining is directly applicable to Resource Conservation and Recovery Act (RCRA) Remedial Facility Investigation/Corrective Measure Study (RFI/CMS) as well. The US Department of Energy's (DOE's) environmental restoration process promises to be lengthy and expensive: therefore, the Office of Environmental Restoration (EM-40) believes that it is to incorporate streamlining into RI/FS and RFI/CMS efforts across the DOE complex. The Office of Program Support (EM-43) has asked Pacific Northwest Laboratory (PNL) to provide presentations and workshops on streamlining ...
1992-06-01
OZONE PRODUCTION IN THE PHILADELPHIA URBAN AREA DURING NE-OPS 99
International Nuclear Information System (INIS)
As part of the 1999 NARSTO Northeast Oxidant and Particulate Study (NE-OPS) field campaign, the DOE G-1 aircraft sampled trace gases and aerosols in and around the Philadelphia metropolitan area. Twenty research flights were conducted between July 25 and August 11. The overall goals of these flights were to obtain a mechanistic understanding of O(sub 3) production; to characterize the spatial and temporal behavior of photo-oxidants and aerosols; and to study the evolution of aerosol size distributions, including the process of new particle formation. Within the NE-OPS program, other groups provided additional trace gas, aerosol, and meteorological observations using aircraft, balloon, remote sensing, and surface based instruments (Phillbrick et al., 2000). In this article we provide an overview of the G-1 observations related to O(sub 3) production, focusing on the vertical distribution of pollutants. Ozone production rates are calculated using a box model that is ...
Energy Technology Data Exchange (ETDEWEB)
A testing program has been conducted by the Westinghouse Hanford Company to confirm the baseline waste form selection for use in Waste Receiving and Processing (WRAP) Module 2A. WRAP Module 2A will provide treatment required to properly dispose of containerized contact-handled, mixed low-level waste at the US Department of Energy Hanford Site in south-central Washington State. Solidification/stabilization has been chosen as the appropriate treatment for this waste. This work is intended to test cement-based, thermosetting polymer, and thermoplastic polymer solidification media to substantiate the technology approach for WRAP Module 2A. Screening tests were performed using the major chemical constituent of each waste type to measure the gross compatibility with the immobilization media and to determine formulations for more detailed testing. Surrogate materials representing each of the eight waste types were prepared in the laboratory. These surrogates were then ...
1993-10-01
Materials considerations for the National Spallation Neutron Source target
Energy Technology Data Exchange (ETDEWEB)
The National Spallation Neutron Source (NSNS), in which neutrons are generated by bombarding a liquid mercury target with 1 GeV protons, will place extraordinary demands on materials performance. The target structural material will operate in an aggressive environment, subject to intense fluxes of high energy protons, neutrons, and other particles, while exposed to liquid mercury and to water. Components that require special consideration include the Hg liquid target container and protective shroud, beam windows, support structures, moderator containers, and beam tubes. In response to these demands a materials R and D program has been developed for the NSNS that includes: selection of materials; calculations of radiation damage; irradiations, post irradiation testing, and characterization; compatibility testing and characterization; design and implementation of a plan for monitoring of materials performance in service; and materials engineering and technical ...
1997-08-01
Low-cost FPSO for service in the Zaafarana oil field
Energy Technology Data Exchange (ETDEWEB)
The Zaafarana oilfield development, operated by Zaafarana Oil Co. (Zafco) presented a series of unique challenges, including redeployment of an internal-turret mooring system, use of a turret-based electrical-cable jumper system, and permanent use of cable-deployed electric submersible pumps in the gravel-pack well completions. Following a detailed three-dimensional (3D) seismic program, the field was discovered by the first well in December 1990. Four subsequent appraisal wells were drilled. The discovery well and two of the appraisal wells tested oil at rates ranging from 2,000 to 10,100 B/D. Initial development plans called for the use of two conventional platforms with a pipeline to a shore-based treatment and storage terminal. Data acquired from subsequent wells were incorporated into the mapping and reserve estimates resulting in a sharp downgrade of the estimated recoverable reserves. The reduced estimate, combined with a revised pricing scenario, ...
1997-04-01
Future Accelerators, Muon Colliders, and Neutrino Factories
Energy Technology Data Exchange (ETDEWEB)
Particle physics is driven by five great topics. Neutrino oscillations and masses are now at the fore. The standard model with extensions to supersymmetry and a Higgs to generate mass explains much of the field. The origins of CP violation are not understood. The possibility of extra dimensions has raised tantalizing new questions. A fifth topic lurking in the background is the possibility of something totally different. Many of the questions raised by these topics require powerful new accelerators. It is not an overstatement to say that for some of the issues, the accelerator is almost the experiment. Indeed some of the questions require machines beyond our present capability. As this volume attests, there are parts of the particle physics program that have been significantly advanced without the use of accelerators such as the subject of neutrino oscillations and many aspects of the particle-cosmology interface. At this stage in the development of physics, both ...
2001-12-19
First RAVEN flight set for September
Energy Technology Data Exchange (ETDEWEB)
An unmanned aerial vehicle called RAVEN, said to be capable of remote tracking of onshore and offshore oil and gas facilities, has been developed by a group of graduate students from Memorial University of Newfoundland. RAVEN is claimed to be capable of performing a number of tasks under its own control without the need for human intervention, including checking onshore pipelines for damage, or scouting the path of hazardous icebergs offshore. The RAVEN was created to meet the need for real time iceberg tracking and early hazard detection, supplementing or replacing the present method of RADARSAT images and tracking by manned aircraft. The RAVEN can be launched from any platform; it can fly under conditions that would be too dangerous for a manned aircraft. Currently in the prototype stage, the first trial flight for the RAVEN is expected to take place in September 2002. The first flight will consist of five GPS waypoints set relatively close together in a pattern ...
2002-08-01
Environmental management plan for the Jhario coalfield - India
Energy Technology Data Exchange (ETDEWEB)
An Environmental Management Plan (EMP) for the Jharia Coalfield (JCF) was recently completed as part of a World Bank funded project. The JCF, 260 km west of Calcutta, comprises 450 km{sup 2}. Bharat Coking Coal Limited (BCCL) operates an area of 258 km{sup 2}. Coal mining has been conducted for more than 100 years. There are severe constraints to mining due to geology, coal fires and the large population. BCCL counterpart staff participated actively in all aspects of the work. Air and water are heavily polluted, however, mining operations contribute only to a limited extent to the total pollution. Water contamination is generally due to inadequate sewage treatment and discharge from non-mine facilities such as power plants. The large area disturbed by mining to date will increase, as open pit mining operations are expected to expand significantly. Reclamation to date is generally confined to planting of trees. Areas where cost effective reclamation can be done were ...
1997-12-31
Dry coke quenching study. Final report, September 1978
The financial evaluation of capital and operating cost estimates for a dry coke quenching facility installation indicates a marginal return on investment if the evaluation is based exclusively on steam credits. However, the potential improvements in environmental emissions and reported, but unverified, blast furnace operations may justify the expenditure. The Russian and Japanese claim of 2 to 4% reduction in blast furnace coke usage with up to 4% increase in iron production has not been demonstrated in the domestic steel industry and, therefore, is not included in the financial analysis. A 2% coke reduction represents a savings of approximately $0.81 per ton of hot metal produced or an additional annual credit of $1,800,000 for dry coke quenching, exclusive of productivity gains. Additional credit of this magnitude would increase the estimated discounted cash flow return from 10% to approximately 16% for the estimated capital expenditure of $21,742,652. The ...
1978-09-01
Development of PHWR fuel fabrication in Korea
Energy Technology Data Exchange (ETDEWEB)
Korea Advanced Energy Research Institute (KAERI) started a research project to develop the PHWR (CANDU) nuclear fuel fabrication technology in 1981. Based on the results of the intensive developmental work, several prototype fuel bundles were fabricated and tested in the Hot Test Loop at KAERI continuously in 1983 and 1984. After that, irradiation test and post-irradiation examination were carried out for two KAERI-made fuel bundles at Chalk River Nuclear Laboratories in Canada in 1984. Since the results of in-pile and out-of-pile tests with prototype fuel bundles proved to be satisfactory, 48 additional fuel bundles were loaded in Wolsung reactor (CANDU) in 1984 and 1985, and all of them were discharged without a defect after excellent performance in the power reactor. In 1985, the Korean government decided that KAERI supplies all the fuel necessary for the Wolsung reactor. For the mass production of nuclear fuel bundle, several process equipment, facilities and ...
1988-01-01
GAO's review of the H-Coal and Exxon projects showed inadequacies in DOE's contracting practices and a failure by DOE to properly plan, manage, and monitor, especially the H-Coal project. The initial Government-industry H-Coal agreements regarding the level of investment by private sponsors and the ceilings imposed on sharing in cost growth were imbalanced. Larger investments by private sponsors and sharing of cost growth provides an incentive to private sponsors to control costs and helps to assure that each party is fully committed to the success of the project. DOE started the H-Coal project prematurely before sufficiently detailed designs were available and without adequate project planning for functions such as construction scheduling, materials handling, inventory systems, and quality control. DOE staffing was inadequate at both projects to effectively monitor progress and contribute to timely decisions. Its contracts for the H-Coal plants were poorly written ...
1981-02-04
Energy Technology Data Exchange (ETDEWEB)
Factors important in choosing between process concepts were mechanical complexity and amenability to scale-up studies. The culmination of this work was a process concept known as Staged Turbulent Bed Retorting Process (STB), which has now been tested in pilot plants. Operating conditions are described. The environment in the retort section can be described as a staged, moving bed of particles, in which a portion of the particles are fluidized at gas velocities well below minimum fluidization velocity of many of the particles. Research and engineering evaluations have established that the STB provides prospects for the responsible development of oil shale resources on a commercial scale. A 320 ton/d semiworks unit, the next technological step, will be commissioned shortly. This unit will be large enough to provide scale-up data for design of modules and to demonstrate the entire process, generating data needed to optimize, design, and construct commercial oil shale ...
1982-03-01
Brookhaven highlights. [Fiscal year 1992, October 1, 1991--September 30, 1992
Energy Technology Data Exchange (ETDEWEB)
This publication provides a broad overview of the research programs and efforts being conducted, built, designed, and planned at Brookhaven National Laboratory. This work covers a broad range of scientific disciplines. Major facilities include the Alternating Gradient Synchrotron (AGS), with its newly completed booster, the National Synchrotron Light Source (NSLS), the High Flux Beam Reactor (HFBR), and the RHIC, which is under construction. Departments within the laboratory include the AGS department, accelerator development, physics, chemistry, biology, NSLS, medical, nuclear energy, and interdepartmental research efforts. Research ranges from the pure sciences, in nuclear physics and high energy physics as one example, to environmental work in applied science to study climatic effects, from efforts in biology which are a component of the human genome project to the study, production, and characterization of new materials. The paper provides ...
1992-12-31
Energy Technology Data Exchange (ETDEWEB)
This publication provides a broad overview of the research programs and efforts being conducted, built, designed, and planned at Brookhaven National Laboratory. This work covers a broad range of scientific disciplines. Major facilities include the Alternating Gradient Synchrotron (AGS), with its newly completed booster, the National Synchrotron Light Source (NSLS), the High Flux Beam Reactor (HFBR), and the RHIC, which is under construction. Departments within the laboratory include the AGS department, accelerator development, physics, chemistry, biology, NSLS, medical, nuclear energy, and interdepartmental research efforts. Research ranges from the pure sciences, in nuclear physics and high energy physics as one example, to environmental work in applied science to study climatic effects, from efforts in biology which are a component of the human genome project to the study, production, and characterization of new materials. The paper provides ...
1992-01-01
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