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HYDRODYNAMIC MODELS FOR SLURRY BUBBLE COLUMN REACTORS. FINAL TECHNICAL REPORT ALSO INCLUDES THE QUARTERLY TECHNICAL REPORT FOR THE PERIOD 01/01/1997 - 03/31/1997.

Description: The objective of this study is to develop a predictive experimentally verified computational fluid dynamic (CFD) three phase model. It predicts the gas, liquid and solid hold-ups (volume fractions) and flow patterns in the industrially important bubble-coalesced (churn-turbulent) regime. The input into the model can be either particulate viscosities as measured with a Brookfield viscometer or effective restitution coefficient for particles. A combination of x-ray and {gamma}-ray densitometers w… more
Date: August 15, 1997
Creator: GIDASPOW, DIMITRI
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The RERTR program.

Description: The Reduced Enrichment Research and Test Reactor (RERTR) Program was established in 1978 at the Argonne National Laboratory (ANL) by the Department of Energy (DOE), which continues to fund the program and to manage it in coordination with the Department of State (DOS), the Arms Control and Disarmament Agency (ACDA), and the Nuclear Regulatory Commission (NRC). The primary objective of the program is to develop the technology needed to use Low-Enrichment Uranium (LEU) instead of High-Enrichment … more
Date: November 14, 1997
Creator: Travelli, A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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THERMAL EVALUATION OF THE USE OF BWR MOX SNF IN THE WASTE PACKAGE DESIGN (SCPB: N/A)

Description: This analysis is prepared by the Mined Geologic Disposal System (MGDS) Waste Package Development Department (WPDD) as specified in the Waste Package Implementation Plan (pp. 4-8,4-11,4-24, 5-1, and 5-13; Ref. 5.10) and Waste Package Plan (pp. 3-15,3-17, and 3-24; Ref. 5.9). The design data request addressed herein is: (1) Characterize the conceptual 40 BWR and 24 BWR Multi-Purpose Canister (MPC) Waste Package (WP) design to show that the design is feasible for use in the MGDS environment when l… more
Date: January 23, 1997
Creator: Wang, H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The LEU conversion status of U.S. Research Reactors.

Description: This paper summarizes the conversion status of US research and test reactors and estimates uranium densities needed to convert reactors with power levels 21 MW from HEU ({ge} 20% U-235) to LEU (<20% U-235) fuels. Detailed conversion studies for each reactor need to be completed in order to establish the feasibility of using LEU fuels.
Date: November 14, 1997
Creator: Matos, J. E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Dissolution of low-enriched UO{sub 2}/Al dispersion plates in alkaline peroxide solution.

Description: Some conclusions from this report are: (1) A UO{sub 2}/Al dispersion target can be successfully dissolved in alkaline peroxide solutions; (2) after destruction of the peroxide recovery of the {sup 99}Mo would be nearly identical to existing processes using basic dissolution; (3) a low-enriched UO{sub 2}/Al dispersion targets could potentially be used for the production of {sup 99}Mo; and (4) punched cores from a UO{sub 2}/Al dispersion target will be irradiated to low-level burnup and effects o… more
Date: October 21, 1997
Creator: Aase, S.; Conner, C.; Landsberger, S.; Vandegrift, G. F.; Wu, D. & Wygmans, D. G.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Design and fabrication of high density uranium dispersion fuels.

Description: Twelve different uranium alloys and compounds with uranium densities greater than 13.8 g/cc were fabricated into fuel plates. Sixty-four experimental fuel plates, referred to as microplates, with overall dimensions of 76.2 mm x 22.2 mm x 1.3 mm and elliptical fuel zone of nominal dimensions of 51 mm x 9.5 mm, began irradiation in the Advanced Test Reactor on August 23, 1997. The fuel test matrix consists of machined or comminuted (compositions are in weight%) U-10Mo,U-8Mo, U-6Mo, U-4Mo, U-9Nb-3… more
Date: November 5, 1997
Creator: Clark, C. R.; McGann, D. J.; Meyer, M. K.; Trybus, C. L. & Wiencek, T. C.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Sampling and Analysis Plan for the 105-N Basin Water

Description: This sampling and analysis plan defines the strategy, and field and laboratory methods that will be used to characterize 105-N Basin water. The water will be shipped to the 200 Area Effluent Treatment Facility for treatment and disposal as part of N Reactor deactivation. These analyses are necessary to ensure that the water will meet the acceptance criteria of the ETF, as established in the Memorandum of Understanding for storage and treatment of water from N-Basin (Appendix A), and the charact… more
Date: December 31, 1997
Creator: Mahood, R.O.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Shielding analysis for the 300 area light water reactor spent nuclear fuel within a modified multi-canister overpack canister in a modified multi-canister overpack cask

Description: Spent light water reactor fuel is to be moved out of the 324 Building. It is anticipated that intact fuel assemblies will be loaded in a modified Multi-Canister Overpack Canister, which in turn will be placed in an Overpack Transportation Cask. An estimate of gamma ray dose rates from a transportation cask is desired.
Date: April 11, 1997
Creator: Gedeon, S.R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Recriticality energetics of a hypothetical water reflood accident in a damaged light water reactor

Description: The Three Mile Island (TMI-2) accident in 1979 resulted in approximately 45% of the fuel collapsing into an irregularly-shaped debris bed near the center of the core, while some of the molten material flowed into the lower dome of the reactor vessel where it solidified. The immediate cause of this severely degraded geometry was loss of coolant and subsequent heatup of the fuel from decay heat. The neutron chain reaction had shut down prior to fuel relocation (below 5 wt% {sup 235}U enrichment, … more
Date: April 24, 1997
Creator: Schwinkendorf, K. N.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

CRC DEPLETION CALCULATIONS FOR THE RODDED ASSEMBLIES IN BATCHES 1, 2, 3, AND 1X OF CRYSTAL RIVER UNIT 3

Description: The purpose of this design analysis is to document the SAS2H depletion calculations of certain rodded fuel assemblies from batches 1, 2, 3, and 1X of the Crystal River Unit 3 pressurized water reactor (PWR) that are required for Commercial Reactor Critical (CRC) evaluations to support the development of the disposal criticality methodology. A rodded assembly is one that contains a control rod assembly (CRA) or an axial power shaping rod assembly (APSRA) for some period of time during its irradi… more
Date: September 3, 1997
Creator: Wright, Kenneth D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

CRC DEPLETION CALCULATIONS FOR THE NON-RODDED ASSEMBLIES IN BATCHES 4 AND 5 OF CRYSTAL RIVER UNIT 3

Description: The purpose of this design analysis is to document the SAS2H depletion calculations of certain non-rodded fuel assemblies from batches 4 and 5 of the Crystal River Unit 3 pressurized water reactor (PWR) that are required for commercial Reactor Critical (CRC) evaluations to support the development of the disposal criticality methodology. A non-rodded assembly is one which never contains a control rod assembly (CRA) or an axial power shaping rod assembly (APSRA) during its irradiation history. Th… more
Date: July 30, 1997
Creator: Wright, Kenneth D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

CRC DEPLETION CALCULATIONS FOR THE NON-RODDED ASSEMBLIES IN BATCHES 1, 2, AND 3 OF CRYSTAL RIVER UNIT 3

Description: The purpose of this design analysis is to document the SAS2H depletion calculations of certain non-rodded fuel assemblies from batches 1, 2, and 3 of the Crystal River Unit 3 pressurized water reactor (PWR) that are required for Commercial Reactor Critical (CRC) evaluations to support development of the disposal criticality methodology. A non-rodded assembly is one which never contains a control rod assembly (CRA) or an axial power shaping rod assembly (APSRA) during its irradiation history. Th… more
Date: July 29, 1997
Creator: Wright, Kenneth D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Construction safety program for the National Ignition Facility

Description: The Construction Safety Program (CSP) for NIF sets forth the responsibilities, guidelines, rules, policies and regulations for all workers involved in the construction, special equipment installation, acceptance testing, and initial activation and operation of NIF at LLNL during the construction period of NIF. During this period, all workers are required to implement measures to create a universal awareness which promotes safe practice at the work site, and which will achieve NIF`s management o… more
Date: January 1, 1997
Creator: Cerruti, Steven J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Investigations in Gallium Removal

Description: Gallium present in weapons plutonium must be removed before it can be used for the production of mixed-oxide (MOX) nuclear reactor fuel. The main goal of the preliminary studies conducted at Texas A and M University was to assist in the development of a thermal process to remove gallium from a gallium oxide/plutonium oxide matrix. This effort is being conducted in close consultation with the Los Alamos National Laboratory (LANL) personnel involved in the development of this process for the US D… more
Date: November 1, 1997
Creator: Philip, C. V.; Pitt, W. W. & Beard, C. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Annual Report in Compliance with the Reactor Sharing Program, September 1, 1994--August 31, 1995

Description: This report contains information with regard to facilities utilization, descriptions (brief), personnel, organization, and programs of the Neely Nuclear Research Center (NNRC) at the Georgia Institute of Technology. The NNRC has two major facilities: the Georgia Tech Research Reactor and the Hot Cell Laboratory. This report of NNRC utilization is prepared in compliance with the contract requirements between the U.S. Department of Energy and the Georgia Institute of Technology. The NNRC is a par… more
Date: April 1, 1997
Creator: Karam, R.A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Structural concerns in dynamic drop loads on transfer lock mechanisms

Description: Drop loads are usually low probability events that can generate substantial loading to the impacted structures. When the impacted structure contains slender elements, the concern about dynamic buckling must be addressed. The problem of interest here is a structure is also under significant preload, which must be taken into account in the transient analysis. For complex structures, numerical simulations are the only viable option for assessing the transient response to short duration impactive l… more
Date: July 1, 1997
Creator: Pfeiffer, P. A.; Moran, T. J. & Kulak, R. F.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Engineering Development of Slurry Bubble Column Reactor (Sbcr) Technology. Quarterly Report, October 1--December 31, 1995

Description: The major technical objectives of this program are threefold: (1) to develop the design tools and a fundamental understanding of the fluid dynamics of a slurry bubble column reactor to maximize reactor productivity, (2) to develop the mathematical reactor design models and gain an understanding of the hydrodynamic fundamentals under industrially relevant process conditions, and (3) to develop an understanding of the hydrodynamics and their interaction with the chemistries occurring in the bubbl… more
Date: December 31, 1997
Creator: Toseland, B. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Engineering Development of Slurry Bubble Column Reactor (Sbcr) Technology. Quarterly Report, April 1--June 30, 1997

Description: The major technical objectives of this program are threefold: (1) to develop the design tools and a fundamental understanding of the fluid dynamics of a slurry bubble column reactor to maximize reactor productivity, (2) to develop the mathematical reactor design models and gain an understanding of the hydrodynamic fundamentals under industrially relevant process conditions, and (3) to develop an understanding of the hydrodynamics and their interaction with the chemistries occurring in the bubbl… more
Date: December 31, 1997
Creator: Toseland, B. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Continuous chemical reaction chromatography. Final report

Description: The research supported by DOE under this grant resulted in the development of continuous flow adsorptive chemical reactors based on chromatographic separations. In particular, the countercurrent moving bed chromatographic reactor and the simulated countercurrent moving bed chromatographic reactor were investigated both theoretically and experimentally. An important contribution was the demonstration that simulated countercurrent moving bed reactors can be successfully used for methane conversio… more
Date: August 1, 1997
Creator: Carr, R.W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Kinetics of MN-based sorbents for hot coal gas desulfurization. Semiannual report, December 15, 1996--March 15, 1997

Description: Manganese-based sorbents have been investigated for the removal of hydrogen sulfide (the primary sulfur bearing compound) from hot coal gases prior to its use in combined cycle turbines. Four formulations of Mn-based sorbents were tested in an ambient-pressure fixed-bed reactor to determine steady state H{sub 2}S concentrations, breakthrough times and effectiveness of the sorbent when subjected to cyclic sulfidation and regeneration testing. In previous reports, the sulfidation and regeneration… more
Date: March 1, 1997
Creator: Hepworth, M.T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Nuclear fuel elements made from nanophase materials

Description: A nuclear reactor core fuel element is composed of nanophase high temperature materials. An array of the fuel elements in rod form are joined in an open geometry fuel cell that preferably also uses such nanophase materials for the cell structures. The particular high temperature nanophase fuel element material must have the appropriate mechanical characteristics to avoid strain-related failure even at high temperatures, in the order of about 3,000 F. Preferably, the reactor type is a pressurize… more
Date: December 1, 1997
Creator: Heubeck, Norman B.
Item Type: Refine your search to only Patent
Partner: UNT Libraries Government Documents Department
open access

Depletion calculations for the McClellan Nuclear Radiation Center.

Description: Depletion calculations have been performed for the McClellan reactor history from January 1990 through August 1996. A database has been generated for continuing use by operations personnel which contains the isotopic inventory for all fuel elements and fuel-followed control rods maintained at McClellan. The calculations are based on the three-dimensional diffusion theory code REBUS-3 which is available through the Radiation Safety Information Computational Center (RSICC). Burnup-dependent cross… more
Date: December 8, 1997
Creator: Klann, R. T. & Newell, D. L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

3RD WP PROBABILISTIC CRITICALITY ANALYSIS: METHODOLOGY FOR BASKET DEGRADATION WITH APPLICANTION TO COMMERICAL SNF

Description: This analysis is prepared by the Mined Geologic Disposal System (MGDS) Waste Package Development (WPD) department to describe the latest version of the probabilistic criticality analysis methodology and its application to the entire commercial waste stream of commercial pressurized water reactor (PWR) spent nuclear fuel (SNF) expected to be emplaced in the repository. The purpose of this particular application is to evaluate the 21 assembly PWR absorber plate waste package (WP) with respect to … more
Date: September 15, 1997
Creator: Goulib, P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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