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Gas Centrifuge Enrichment Plant seismic time history development

Description: The objective of this study is to generate a number of artificial-spectrum consistent-time histories for use in the seismic analysis of the Gas Centrifuge Enrichment Plant (GCEP) service modules (SM). The method used in the generation of the artificial time histories presented in this report makes use of the fast Fourier transform (FFT) algorithm to modify the Fourier frequency spectrum of a recorded accelerogram. The response spectrum of the generated accelerogram is consistent with the spectrum specification given by USAEC Regulatory Guide 1.60. Five statistically independent time histories have been developed. These accelerograms are based on recorded West Coast accelerations that meet specific requirements associated with the location of the recording station with regard to the epicenter. The acceleration time history, Fourier and response spectras, and integrated velocity and displacement records are presented.
Date: July 1, 1979
Creator: Aramayo, G.A. & Carley, T.G.
Partner: UNT Libraries Government Documents Department

Impact analysis of spent fuel jacket assemblies

Description: As part of the analyses performed in support of the reracking of the High Flux Isotope Reactor pool, it became necessary to prove the structural integrity of the spent fuel jacket assemblies subjected to gravity drop that result from postulated accidents associated with the handling of these assemblies while submerged in the pool. The spent fuel jacket assemblies are an integral part of the reracking project, and serve to house fuel assemblies. The structure integrity of the jacket assemblies from loads that result from impact from a height of 10 feet onto specified targets has been performed analytically using the computer program LS-DYNA3D. Nine attitudes of the assembly at the time of impact have been considered. Results of the analyses show that there is no failure of the assemblies as a result of the impact scenarios considered.
Date: June 1, 1994
Creator: Aramayo, G. A.
Partner: UNT Libraries Government Documents Department

Impact analysis of the DC-1 shipping container

Description: Containers used by the Department of Energy (DOE) for the transport of radioactive material components, including components and special assemblies, are required to meet certain impact requirements that are demonstrated by experimental testing, analytical modeling, or the combination of both. The Code of Federal Regulations (CFR) Part 49 Section 173.7(d) stipulates that, packages (containers) made by or under direction of the USDOE may be used for the transportation of radioactive materials when evaluated, approved, and certified by the DOE against packaging standards equivalent to those specified in 10 CFR Part 71.1 This paper gives an example of computer analysis of the impact simulation for a typical container in support of experimental testing performed to assure compliance of the container design with Federal Regulations. The paper includes details of the analysis performed and lists the advantages and disadvantages compared with experimental testing.
Date: June 1, 1994
Creator: Aramayo, G. A.
Partner: UNT Libraries Government Documents Department

Guidelines for ground motion definition for the eastern United States

Description: Guidelines for the determination of earthquake ground motion definition for the eastern United States are established here. Both far-field and near-field guidelines are given. The guidelines were based on an extensive review of the current procedures for specifying ground motion in the United States. Both empirical and theoretical procedures were used in establishing the guidelines because of the low seismicity in the eastern United States. Only a few large- to great-sized earthquakes (M/sub s/ > 7.5) have occurred in this region, no evidence of tectonic surface ruptures related to historic or Holocene earthquakes has been found, and no currently active plate boundaries of any kind are known in this region. Very little instrumented data have been gathered in the East. Theoretical procedures are proposed so that in regions of almost no data, a reasonable level of seismic ground motion activity can be assumed. The guidelines are to be used to develop the safe shutdown earthquake (SSE). A new procedure for establishing the operating basis earthquake (OBE) is proposed, in particular for the eastern United States. The OBE would be developed using a probabilistic assessment of the geological conditions and the recurrence of seismic events at a site. These guidelines should be useful in development of seismic design requirements for future reactors. 17 refs., figs., tabs.
Date: June 1, 1985
Creator: Gwaltney, R.C.; Aramayo, G.A. & Williams, R.T.
Partner: UNT Libraries Government Documents Department

Guidelines for earthquake ground motion definition for the eastern United States

Description: Guidelines for the determination of earthquake ground-motion definition for the eastern United States are established in this paper. Both far-field and near-field guidelines are given. The guidelines were based on an extensive review of the current procedures for specifying ground motion in the United States. Both empirical and theoretical procedures were used in establishing the guidelines because of the low seismicity in the eastern United States. Only a few large to great (M > 7.5) sized earthquakes have occurred in this region, no evidence of tectonic surface ruptures related to historic or Holocene earthquakes have been found, and no currently active plate boundaries of any kind are known in this region. Very little instrumented data has been gathered in the East. Theoretical procedures are proposed so that in regions of almost no data a reasonable level of seismic ground motion activity can be assumed. The guidelines are to be used to develop the Safe Shutdown Earthquake, SSE. A new procedure for establishing the Operating Basis Earthquake, OBE, is proposed, in particular for the eastern United States. The OBE would be developed using a probabilistic assessment of the geological conditions and the recurrence of seismic events at a site. These guidelines should be useful in development of seismic design requirements for future reactors. 17 refs., 2 figs., 1 tab.
Date: January 1, 1985
Creator: Gwaltney, R.C.; Aramayo, G.A. & Williams, R.T.
Partner: UNT Libraries Government Documents Department

The DT-19 container: Design, impact testing and analysis

Description: Containers used by the Department of Energy (DOE) for the transport of radioactive material components, including components and special assemblies, are required to meet certain impact and thermal requirements that are demonstrated by performance or compliance testing, analytical procedures or a combination of both. The Code of Federal Regulations (CFR) Part 49, Section 173.7(d) stipulates that, `Packages (containers) made by or under direction of the U.S. DOE may be used for the transportation of radioactive materials when evaluated, approved, and certified by the DOE against packaging standards equivalent to those specified in 10 CFR Part 71.` This paper describes the details of the design, analysis and testing efforts undertaken to improve the overall structural and thermal integrity of the DC-19 shipping container.
Date: July 1, 1996
Creator: Aramayo, G.A. & Goins, M.L.
Partner: UNT Libraries Government Documents Department

The DT-19 container design, impact testing and analysis

Description: Containers used by the Department of Energy (DOE) for the transport of radioactive material components, including components and special assemblies, are required to meet certain impact and thermal requirements that are demonstrated by performance or compliance testing, analytical procedures or a combination of both. The Code of Federal Regulations (CFR) Part 49, Section 173.7(d) stipulates that, {prime}Packages (containers) made by or under direction of the US DOE may be used for the transportation of radioactive materials when evaluated, approved, and certified by the DOE against packaging standards equivalent to those specified in 10 CFR Part 71. This paper describes the details of the design, analysis and testing efforts undertaken to improve the overall structural and thermal integrity of the DC-19 shipping container.
Date: December 1, 1995
Creator: Aramayo, G.A. & Goins, M.L.
Partner: UNT Libraries Government Documents Department

Development of site-specific synthetic accelerations for safety assessment of DOE facilities at Oak Ridge, Tennessee

Description: Seismic analysis of US Department of Energy (DOE) facilities at Oak Ridge, TN, requires seismic accelerograms that have response spectra that are compatible with the site-specific design response spectra. The development of these accelerograms is accomplished by the application of the Fourier transform to compute the response spectrum of a beginning accelerogram and map it into the frequency domain. The Fourier spectrum is modified according to the difference between the computed spectra and the target spectra. The response spectrum is recomputed and compared again to the target. The modification is repeated until acceptable agreement is achieved. The modified Fourier spectrum is transformed to the time domain and filtered yielding the desired seismic time history. 7 refs., 5 figs.
Date: January 1, 1991
Creator: Aramayo, G.A.; Carley, T.G. & Jones, W.D.
Partner: UNT Libraries Government Documents Department

Impact analysis of stainless steel spent fuel canisters

Description: This paper presents the results of the numerical analysis performed to asses the structural integrity of spent nuclear fuel (SNF) stainless steel canisters when subjected to impact loads associated with free gravity drops from heights not exceeding 20 ft. The SNF canisters are to be used for the Shipment of radioactive material from the Oak Ridge National Laboratory (ORNL) Site to the Idaho National Engineering and Environmental Laboratory (INEEL) for storage. The Idaho chemical Processing Plant Fuel Receipt Criteria Questionnaire requires that the vertical drop accidents from two heights be analyze. These heights are those that are considered to be critical at the time of unloading the canisters from the shipping cask. The configurations analyzed include a maximum payload of 90 lbs dropping from heights of 20 and 3 ft. The nominal weight of the canister is 23.3 lbs. The analysis has been performed using finite element methods. Innovative analysis techniques are used to capture the effects of failure and separation of canister components. The structural integrity is evaluated in terms of physical deformation and separation of the canister components that may result from failure of components at selected interfaces.
Date: April 1998
Creator: Aramayo, G. A. & Turner, D. W.
Partner: UNT Libraries Government Documents Department

Thermal simulation of quenching uranium-0. 75% titanium alloy in water

Description: A computer model, The Quench Simulator, has been developed to simulate and predict in detail the behavior of U-0.75 Ti alloy when quenched at high temperature (about 850/sup 0/C) in cold water. The code allows one to determine the time- and space-dependent distributions of temperature, residual stress, distortion, and microstructure that evolve during the quenching process. The nonlinear temperature- and microstructure-dependent properties, as well as the cooling rate-dependent heats of transformation, are incorporated into the model. The complex boiling heat transfer with its various regimes and other thermal boundary conditions are simulated. Experiments have been performed and incorporated into the model. Both sudden submersion and gradual controlled immersion can be applied. A parametric and sensitivity study has been performed demonstrating the importance of the thermal boundary conditions applied for achieving certain product characteristics. The thermal aspects of the model and its applications are discussed and demonstrated.
Date: January 1, 1985
Creator: Siman-Tov, M.; Llewellyn, G.H.; Childs, K.W.; Ludtka, G.M. & Aramayo, G.A.
Partner: UNT Libraries Government Documents Department

Safety analysis report for packaging (SARP) of the Oak Ridge National Laboratory. TRU curium shipping container

Description: An analytical evaluation of the Oak Ridge National Laboratory Transuranium (TRU) Curium Shipping Container was made to demonstrate its compliance with the regulations governing offsite shipment of packages containing radioactive material. The evaluation encompassed five primary categories: structural integrity, thermal resistance, radiation shielding, nuclear criticality safety, and quality assurance. The results of the evaluation show that the container complies with the applicable regulations.
Date: June 1, 1980
Creator: Box, W.D.; Klima, B.B.; Seagren, R.D.; Shappert, L.B. & Aramayo, G.A.
Partner: UNT Libraries Government Documents Department

Safety Analysis Report for Packaging (SARP) of the Oak Ridge National Laboratory Garden Carrier No. 2. Revision 1

Description: An analytical evaluation of the Oak Ridge National Laboratory Garden Carrier No. 2 was made to demonstrate its compliance with the regulations governing off-site radioactive material shipping packages. The evaluation encompassed five primary categories: structural integrity, thermal resistance, radiation shielding, nuclear criticality safety, and quality assurance. The results of the evaluation show that the cask complies with the applicable regulations.
Date: August 1, 1979
Creator: Box, W.D.; Klima, B.B.; Seagren, R.D.; Shappert, L.B.; Watson, C.D. & Aramayo, G.A.
Partner: UNT Libraries Government Documents Department

ORNL radioactive carrier drop test facility: the design, construction, and operating capability

Description: A large drop test facility has been constructed at the Tower Shielding Facility (TSF) at the Oak Ridge National Laboratory. A 670- metric ton impact pad was constructed of reinforced concrete and armor plate and located between two 96-m-tall towers of the TSF. The towers, with heavy-duty hoisting equipment attached at their tops, are 39 m apart and are capable of lifting and dropping casks from heights of 60 m. Casks weighing 100 metric tons can be tested at 9 m, whereas lesser weight casks can be handled at greater heights. The design, construction, and operating capability of this facility are desccribed.
Date: January 1, 1978
Creator: Seagren, R.D.; Aramayo, G.A.; Holmes, R.M.; Box, W.D.; Shappert, L.B. & Evans, J.H.
Partner: UNT Libraries Government Documents Department

Advanced computational simulation for design and manufacturing of lightweight material components for automotive applications

Description: Computational vehicle models for the analysis of lightweight material performance in automobiles have been developed through collaboration between Oak Ridge National Laboratory, the National Highway Transportation Safety Administration, and George Washington University. The vehicle models have been verified against experimental data obtained from vehicle collisions. The crashed vehicles were analyzed, and the main impact energy dissipation mechanisms were identified and characterized. Important structural parts were extracted and digitized and directly compared with simulation results. High-performance computing played a key role in the model development because it allowed for rapid computational simulations and model modifications. The deformation of the computational model shows a very good agreement with the experiments. This report documents the modifications made to the computational model and relates them to the observations and findings on the test vehicle. Procedural guidelines are also provided that the authors believe need to be followed to create realistic models of passenger vehicles that could be used to evaluate the performance of lightweight materials in automotive structural components.
Date: April 1, 1997
Creator: Simunovic, S.; Aramayo, G.A.; Zacharia, T.; Toridis, T.G.; Bandak, F. & Ragland, C.L.
Partner: UNT Libraries Government Documents Department

Recent experience in planning, packaging and preparing noncommercial spent fuel for shipment in the United States

Description: The US Department of Energy-Headquarters (DOE-HQ) has issued a Record of Decision (ROD) which identified the plan to be followed in managing spent nuclear fuel (SNF) belonging to the Department. As a result, the aluminum-clad fuels stored at Oak Ridge National Laboratory (ORNL) in Oak Ridge, Tennessee, were directed to be shipped to the Savannah River Site (SRS) near Aiken, South Carolina. The BMI-1 cask was chosen to make the shipments of SNF from dry storage that had to be placed in canisters. However, the Certificate of Compliance (COC) for the BMI-1 cask limited the fissile material loading to 800 g of unirradiated fissile material for the cask configuration chosen. Because about half of the canisters were already filled and sealed with more fissile material than was permitted by the COC, approval to make these shipments in the BMI-1 was requested from the Nuclear Regulatory Commission (NRC). A safety analysis showed that the shipments could be made safely under the conditions identified. The waiver was granted in September 1997 and the three shipments were successfully completed in January 1998.
Date: May 1, 1998
Creator: Shappert, L.B.; Parks, C.V.; Turner, D.W. & Aramayo, G.A.
Partner: UNT Libraries Government Documents Department

Simulation for analysis and control of superplastic forming. Final report

Description: A joint study was conducted by Oak Ridge National Laboratory (ORNL) and the Pacific Northwest Laboratory (PNL) for the U.S. Department of Energy-Lightweight Materials (DOE-LWM) Program. the purpose of the study was to assess and benchmark the current modeling capabilities with respect to accuracy of predictions and simulation time. Two modeling capabilities with respect to accuracy of predictions and simulation time. Two simulation platforms were considered in this study, which included the LS-DYNA3D code installed on ORNL`s high- performance computers and the finite element code MARC used at PNL. both ORNL and PNL performed superplastic forming (SPF) analysis on a standard butter-tray geometry, which was defined by PNL, to better understand the capabilities of the respective models. The specific geometry was selected and formed at PNL, and the experimental results, such as forming time and thickness at specific locations, were provided for comparisons with numerical predictions. Furthermore, comparisons between the ORNL simulation results, using elasto-plastic analysis, and PNL`s results, using rigid-plastic flow analysis, were performed.
Date: August 1, 1996
Creator: Zacharia, T.; Aramayo, G.A.; Simunovic, S.; Ludtka, G.M.; Khaleel, M.; Johnson, K.I. et al.
Partner: UNT Libraries Government Documents Department