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Irradiation Experiment Conceptual Design Parameters for Murr Leu U-MO Fuel Conversion (open access)

Irradiation Experiment Conceptual Design Parameters for Murr Leu U-MO Fuel Conversion

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Date: March 26, 2013
Creator: Stillman, J.; Feldman, E.; Stevens, J.; Wilson, E.; Foyto, L.; Kutikkad, K. et al.
Object Type: Report
System: The UNT Digital Library
Strategy for Multi-Scale Single-Phase Flow Coupling (open access)

Strategy for Multi-Scale Single-Phase Flow Coupling

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Date: May 3, 2013
Creator: Hu, R.; Thomas, J. W. & Fanning, T. H. (Nuclear Engineering Division)
Object Type: Report
System: The UNT Digital Library
Shape-selective catalysts for Fischer-Tropsch chemistry : atomic layer deposition of active catalytic metals. Activity report : January 1, 2005 - September 30, 2005. (open access)

Shape-selective catalysts for Fischer-Tropsch chemistry : atomic layer deposition of active catalytic metals. Activity report : January 1, 2005 - September 30, 2005.

Argonne National Laboratory is carrying out a research program to create, prepare, and evaluate catalysts to promote Fischer-Tropsch (FT) chemistry - specifically, the reaction of hydrogen with carbon monoxide to form long-chain hydrocarbons. In addition to needing high activity, it is desirable that the catalysts have high selectivity and stability with respect to both mechanical strength and aging properties. The broad goal is to produce diesel fraction components and avoiding excess yields of both light hydrocarbons and heavy waxes. Originally the goal was to prepare shape-selective catalysts that would limit the formation of long-chain products and yet retain the active metal sites in a protected 'cage.' Such catalysts were prepared with silica-containing fractal cages. The activity was essentially the same as that of catalysts without the cages. We are currently awaiting follow-up experiments to determine the attrition strength of these catalysts. A second experimental stage was undertaken to prepare and evaluate active FT catalysts formed by atomic-layer deposition [ALD] of active components on supported membranes and particulate supports. The concept was that of depositing active metals (i.e. ruthenium, iron or cobalt) upon membranes with well defined flow channels of small diameter and length such that the catalytic activity and product …
Date: April 15, 2011
Creator: Cronauer, D. C. (Chemical Sciences and Engineering Division)
Object Type: Report
System: The UNT Digital Library
Used Fuel Disposition Campaign Phase I Ring Compression Testing of High-Burnup Cladding (open access)

Used Fuel Disposition Campaign Phase I Ring Compression Testing of High-Burnup Cladding

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Date: March 20, 2013
Creator: Billone, M. C.; Burtseva, T. A.; Dobrzynski, J. P.; McGann, D. P.; Bryne, K.; Han, Z. et al.
Object Type: Report
System: The UNT Digital Library
Used fuel disposition campaign international activities implementation plan. (open access)

Used fuel disposition campaign international activities implementation plan.

The management of used nuclear fuel and nuclear waste is required for any country using nuclear energy. This includes the storage, transportation, and disposal of low and intermediate level waste (LILW), used nuclear fuel (UNF), and high level waste (HLW). The Used Fuel Disposition Campaign (UFDC), within the U.S. Department of Energy (DOE), Office of Nuclear Energy (NE), Office of Fuel Cycle Technology (FCT), is responsible for conducting research and development pertaining to the management of these materials in the U.S. Cooperation and collaboration with other countries would be beneficial to both the U.S. and other countries through information exchange and a broader participation of experts in the field. U.S. participation in international UNF and HLW exchanges leads to safe management of nuclear materials, increased security through global oversight, and protection of the environment worldwide. Such interactions offer the opportunity to develop consensus on policy, scientific, and technical approaches. Dialogue to address common technical issues helps develop an internationally recognized foundation of sound science, benefiting the U.S. and participating countries. The UNF and HLW management programs in nuclear countries are at different levels of maturity. All countries utilizing nuclear power must store UNF, mostly in wet storage, and HLW for …
Date: June 29, 2011
Creator: Nutt, W. M. (Nuclear Engineering Division)
Object Type: Report
System: The UNT Digital Library
OECD MCCI project long-term 2-D molten core concrete interaction test design report, Rev. 0. September 30, 2002. (open access)

OECD MCCI project long-term 2-D molten core concrete interaction test design report, Rev. 0. September 30, 2002.

The Melt Attack and Coolability Experiments (MACE) program at Argonne National Laboratory addressed the issue of the ability of water to cool and thermally stabilize a molten core-concrete interaction when the reactants are flooded from above. These tests provided data regarding the nature of corium interactions with concrete, the heat transfer rates from the melt to the overlying water pool, and the role of noncondensable gases in the mixing processes that contribute to melt quenching. As a follow-on program to MACE, The Melt Coolability and Concrete Interaction Experiments (MCCI) project is conducting reactor material experiments and associated analysis to achieve the following two technical objectives: (1) resolve the ex-vessel debris coolability issue through a program that focuses on providing both confirmatory evidence and test data for the coolability mechanisms identified in MACE integral effects tests, and (2) address remaining uncertainties related to long-term two-dimensional molten core-concrete interactions under both wet and dry cavity conditions. Achievement of these two objectives will demonstrate the efficacy of severe accident management guidelines for existing plants, and provide the technical basis for better containment designs for future plants. In terms of the first program objective, the Small-Scale Water Ingression and Crust Strength (SSWICS) test series …
Date: May 23, 2011
Creator: Farmer, M. T.; Kilsdonk, D. J.; Lomperski, S.; Aeschliman, R. W. & Basu, S.
Object Type: Report
System: The UNT Digital Library
OECD MCCI project Small-Scale Water Ingression and Crust Strength Tests (SSWICS) SSWICS-1 test data report : thermal hydraulic results. Rev. 0 September 20, 2002. (open access)

OECD MCCI project Small-Scale Water Ingression and Crust Strength Tests (SSWICS) SSWICS-1 test data report : thermal hydraulic results. Rev. 0 September 20, 2002.

The Melt Attack and Coolability Experiments (MACE) program at Argonne National Laboratory addressed the issue of the ability of water to cool and thermally stabilize a molten core/concrete interaction (MCCI) when the reactants are flooded from above. These tests provided data regarding the nature of corium interactions with concrete, the heat transfer rates from the melt to the overlying water pool, and the role of noncondensable gases in the mixing processes that contribute to melt quenching. However, due to the integral nature of these tests, several questions regarding the crust freezing behavior could not be adequately resolved. These questions include: (1) To what extent does water ingression into the crust increase the melt quench rate above the conduction-limited rate and how is this affected by melt composition and system pressure and (2) What is the fracture strength of the corium crust when subjected to a thermal-mechanical load and how does it depend upon the melt composition? A series of separate-effects experiments are being conducted to address these issues. The first employs an apparatus designed to measure the quench rate of a pool of corium ({approx}{phi}30 cm; up to 20 cm deep). The main parameter to be varied in these quench …
Date: May 23, 2011
Creator: Lomperski, S.; Farmer, M. T.; Kilsdonk, D. J.; Aeschlimann, R. W. & Basu, S.
Object Type: Report
System: The UNT Digital Library
Recovery of Mo for Accelerator Production of Mo-99 Using (y,n) Reaction on Mo-100 (open access)

Recovery of Mo for Accelerator Production of Mo-99 Using (y,n) Reaction on Mo-100

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Date: February 19, 2014
Creator: Tkac, P.; Vandegrift, G. F.; Nunn, S. D. & Harvey, J.
Object Type: Report
System: The UNT Digital Library
Uranium Anodic Dissolution under Slightly Alkaline Conditions Progress Report Full-Scale Demonstration with DU Foil (open access)

Uranium Anodic Dissolution under Slightly Alkaline Conditions Progress Report Full-Scale Demonstration with DU Foil

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Date: February 18, 2014
Creator: Gelis, A.; Brown, M.A.; Wiedmeyer, S. & Vandegrift, G.F. (Chemical Sciences and Engineering Division)
Object Type: Report
System: The UNT Digital Library
Review of Existing Hydroelectric Turbine-Governor Simulation Models (open access)

Review of Existing Hydroelectric Turbine-Governor Simulation Models

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Date: October 25, 2013
Creator: Feltes, J.; Koritarov, V.; Guzowski, L.; Kazachkov, Y.; Lam, B.; Grande-Moran, C. et al.
Object Type: Report
System: The UNT Digital Library
Using Multi-scale Dynamic Rupture Models to Improve Ground Motion Estimates: ALCF-2 Early Science Program Technical Report (open access)

Using Multi-scale Dynamic Rupture Models to Improve Ground Motion Estimates: ALCF-2 Early Science Program Technical Report

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Date: October 31, 2013
Creator: Ely, G.P. (LCF)
Object Type: Report
System: The UNT Digital Library
Modeling Adjustable Speed Pumped Storage Hydro Units Employing Doubly-Fed Induction Machines (open access)

Modeling Adjustable Speed Pumped Storage Hydro Units Employing Doubly-Fed Induction Machines

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Date: October 25, 2013
Creator: Feltes, J.; Koritarov, V.; Guzowski, L.; Kazachkov, Y.; Gong, B.; Trouille, B. et al.
Object Type: Report
System: The UNT Digital Library
Testing Dynamic Simulation Models for Different Types of Advanced Pumped Storage Hydro Units (open access)

Testing Dynamic Simulation Models for Different Types of Advanced Pumped Storage Hydro Units

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Date: October 25, 2013
Creator: Feltes, J.; Koritarov, V.; Kazachkov, Y.; Gong, B.; Donalek, P.; Gevorgian, V. (Decision and Information Sciences) et al.
Object Type: Report
System: The UNT Digital Library
Reversal of OFI and CHF in Research Reactors Operating at 1 to 50 Bar. Version 1.0 (open access)

Reversal of OFI and CHF in Research Reactors Operating at 1 to 50 Bar. Version 1.0

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Date: February 28, 2014
Creator: Kalimullah, M.; Olson, A. P.; Dionne, B.; Feldman, E. E. & Matos, J. E.
Object Type: Report
System: The UNT Digital Library
Protective Measures Index and Vulnerability Index: Indicators of Critical Infrastructure Protection and Vulnerability (open access)

Protective Measures Index and Vulnerability Index: Indicators of Critical Infrastructure Protection and Vulnerability

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Date: November 21, 2013
Creator: Petit, F. D.; Bassett, G. W.; Buehring, W. A.; Collins, M. J.; Dickinson, D. C.; Haffenden, R. A. et al.
Object Type: Report
System: The UNT Digital Library
Van de Graaff Experiments: Mo Redox Chemistry and Iodine Speciation (open access)

Van de Graaff Experiments: Mo Redox Chemistry and Iodine Speciation

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Date: October 7, 2013
Creator: Youker, A. J.; Krebs, J. F.; Hebden, A.; Quigley, K.; Stepinski, D. & Vandegrift, G. F. (Chemical Sciences and Engineering Division)
Object Type: Report
System: The UNT Digital Library
Testing of a Microfluidic Sampling System for High Temperature Electrochemical MC&A (open access)

Testing of a Microfluidic Sampling System for High Temperature Electrochemical MC&A

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Date: November 27, 2013
Creator: Pereira, C. & Nichols, K. (Chemical Sciences and Engineering Division)
Object Type: Report
System: The UNT Digital Library
NEAMS Update. Quarterly Report for April - June 2013 (open access)

NEAMS Update. Quarterly Report for April - June 2013

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Date: September 27, 2013
Creator: Bradley, K. S.
Object Type: Report
System: The UNT Digital Library
Vài Nét Trợ Cấp Thất Nghiệp (open access)

Vài Nét Trợ Cấp Thất Nghiệp

A Vietnamese-language pamphlet detailing the means and conditions for applying for unemployment benefits as well as steps to take afterward.
Date: February 2013
Creator: Texas Workforce Solutions
Object Type: Pamphlet
System: The Portal to Texas History