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Reactivity-Worth Estimates of the OSMOSE Samples in the MINERVE Reactor R1-MOX, R2-UO2 and MORGANE/R Configurations.

Description: An initial series of calculations of the reactivity-worth of the OSMOSE samples in the MINERVE reactor with the R2-UO2 and MORGANE/R core configuration were completed. The calculation model was generated using the lattice physics code DRAGON. In addition, an initial comparison of calculated values to experimental measurements was performed based on preliminary results for the R1-MOX configuration.
Date: August 3, 2007
Creator: Zhong, Z. & Klann, R. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Reactivity-Worth Estimates of the Osmose Samples in the Minerve Reactor r1-uo2 Configuration.

Description: An initial series of calculations of the reactivity-worth of the OSMOSE samples in the MINERVE reactor with the R1-UO2 core configuration were completed. The reactor model was generated using the REBUS code developed at Argonne National Laboratory. The calculations are based on the specifications for fabrication, so they are considered preliminary until sampling and analysis have been completed on the fabricated samples. The estimates indicate a range of reactivity effect from -22 pcm to +25 pc… more
Date: October 3, 2007
Creator: Klann, R. T. & Perret, G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

SUPERDAN: computer programs for calculating the Dancoff factor of spheres, cylinders, and slabs

Description: Resonance integral calculations for a reactor lattice require the use of the Dancoff factor. In the past, tables and approximate expressions have been used to obtain this value. In order to reduce the uncertainty in the use of approximations and to avoid the inconvenience of tables, a series of computer programs has been written to calculate the Dancoff factor. Three computer programs have been prepared, one each for infinitely long cylinders, spheres, and infinite slabs. The program for cylind… more
Date: March 1, 1978
Creator: Knight, J. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Assessment of the 3430 Building Filtered Exhaust Stack Sampling Probe Location

Description: Pacific Northwest National Laboratory performed a demonstration to determine the acceptable location in which to place an air sampling probe for emissions monitoring for radionuclides in the exhaust air discharge from the new 3430 Building Filtered Exhaust Stack. The method was to adopt the results of a previously performed test series for a system of similar configuration, followed by a partial test on the actual system to verify the applicability of previously performed tests. The qualificati… more
Date: July 16, 2010
Creator: Glissmeyer, John A. & Flaherty, Julia E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Spatial channel theory: A technique for determining the directional flow of radiation through reactor systems

Description: A method is introduced for determining streaming paths through a non-multiplying medium. The concepts of a ''response continuum'' and a pseudo-particle called a contribution are developed to describe the spatial channels through which response flows from a source to a detector. An example application of channel theory to complex shield analysis is cited.
Date: January 1, 1977
Creator: Williams, M. L. & Engle, W. W.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Criticality Calculations for the VR-1 Reactor with IRT-3M-HEU Fuel and IRT-4MLEU Fuel.

Description: At The request of the Czech Technical University in Prague, ANL has performed independent verification calculations using the MCNP Monte Carlo code for three core configurations of the VR-1 reactor: a current core configuration B1 with HEU (36%) IRT-3M fuel assemblies and planned core configurations C1 and C2 with LEU (19.7%) IRT-4M fuel assemblies. Details of these configurations were provided to ANL by CTU. For core configuration B1, criticality calculations were performed for two sets of con… more
Date: January 17, 2007
Creator: Hanan, N. A. & Matos, J. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Plan for Developing and Implementing the LLNL Plutonium Facility and Packaging Program

Description: The LLNL Plutonium Facility uses glove boxes for performing operations involving special nuclear materials (SNM) that for the most part are not connected to each other. Having standalone glove boxes mandates bag-in and bag-out operations to provide personnel safety in material transfers. The use of inexpensive disposable primary and secondary containers (i.e., food pack and paint cans) decreases operational risks by reducing glove box transfers. Typically, containers consist of produce cans, pa… more
Date: March 29, 2005
Creator: Dodson, K E; Burch, J G; Krikorian, O H & Riley, D C
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Further development of the cleanable steel HEPA filter, cost/benefit analysis, and comparison with competing technologies

Description: We have made further progress in developing a cleanable steel fiber HEPA filter. We fabricated a pleated cylindrical cartridge using commercially available steel fiber media that is made with 1 {mu}m stainless steel fibers and sintered into a sheet form. Test results at the Department of Energy (DOE) Filter Test Station at Oak Ridge show the prototype filter cartridge has 99.99% efficiency for 0.3 {mu}m dioctyl phthalate (DOP) aerosols and a pressure drop of 1.5 inches. Filter loading and clean… more
Date: January 1, 1997
Creator: Bergman, W.; Larsen, G.; Lopez, R.; Wilson, K.; Witherell, C. & McGregor, M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Dynamics of two coaxial cylindrical shells containing viscous fluid

Description: This study was motivated by the need to design the thermal shield in reactor internals and other system components to avoid detrimental flow-induced vibrations. The system component is modeled as two coaxial shells separated by a viscous fluid. In the analysis, Flugge's shell equations of motion and linearized Navier-Stokes equation for viscous fluid are employed. First, a traveling-wave type solution is taken for shells and fluid. Then, from the interface conditions between the shells and flui… more
Date: September 1, 1976
Creator: Yeh, T. T. & Chen, S. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Stresses from pressure, radial, and moment loads in cylinder-to-cylinder vessel by a finite plate method

Description: A structural problem that has received continued interest and development over the last several decades is the determination of stresses in two normally intersecting cylindrical shells subjected to internal pressure and external loading. In nuclear pressure vessels the external loading of the vessel through the attachment is encountered in thermal interaction, seismic loading and various postulated rupture or failure mechanisms. A simple technique, the Finite Plate Method, (FPM) is presented to… more
Date: August 1, 1977
Creator: Brown, S. J. & Fox, M. E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Dynamics of a cylindrical shell system coupled by viscous fluid

Description: This study was motivated by the need to design the thermal shield in reactor internals and other system components to avoid detrimental flow-induced vibrations. The system component is modeled as two coaxial shells separated by a viscous fluid. In the analysis, Fluegge's shell equations of motion and linearized Navier--Stokes equation for viscous fluid are employed. First, a traveling-wave type solution is taken for shells and fluid. Then, from the interface conditions between the shells and fl… more
Date: January 1, 1976
Creator: Yeh, T. T. & Chen, S. S.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Stress and Heat Transfer Analyses for Different Channel Arrangements of PCHE

Description: Stress and heat transfer analyses are being performed on the different channel arrangements of Printed Circuit Heat Exchanger (PCHE) proposed for application of VHTRs using ABAQUS [ABAQUS, 2007] and COMSOL [COMSOL, 2007], respectively. The work is being done to determine the configuration that would result in minimum stress for the same heat performance. This paper discusses the effects of shifting the coolant channels in every other row to reduce stress.
Date: November 1, 2008
Creator: Lim, Jong B.; Shrake, Robert G.; Kim, Eung S. & Oh, Chang H.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Effects of foundation modeling on dynamic response of a soil- structure system

Description: This paper presents the results of our investigation to evaluate the effectiveness of different foundation modeling techniques used in soil-structure interaction analyses. The study involved analysis of three different modeling techniques applied to two different foundation configurations (one with a circular and one with a square shape). The results of dynamic response of a typical nuclear power plant structure supported on such foundations are presented.
Date: July 1996
Creator: Chen, J. C. & Tabatabaie, M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Comparison of ELM heat loads in snowflake and standard divertors

Description: An analysis is given of the impact of the tokamak divertor magnetic structure on the temporal and spatial divertor heat flux from edge localized modes (ELMs). Two configurations are studied: the standard divertor where the poloidal magnetic field (B{sub p}) varies linearly with distance (r) from the magnetic null and the snowflake where B{sub p} varies quadratrically with r. Both one and two-dimensional models are used to analyze the effect of the longer magnetic field length between the midpla… more
Date: May 8, 2012
Creator: Rognlien, T. D.; Cohen, R. H.; Ryutov, D. D. & Umansky, M. V.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

The exact solutions to the dynamic response of tanks containing two liquids

Description: The exact solution to the dynamic response of circular cylindrical tanks containing two liquids, considering the gravitational (g) effect at the interface of the two liquids, is presented. Only rigid tanks were studied. The solution is expressed as the superposition of the so-called impulsive and convective solutions. The results are compared with those obtained by neglecting the gravitational effect at the interface to elucidate the g effect and with those of the tanks containing only one liqu… more
Date: February 1, 1993
Creator: Tang, Y. & Chang, Y. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Critical masses of uranium diluted with matrix material

Description: Critical masses of square-prisms of highly enriched uranium diluted in various X/235U ratios with matrix material and polyethylene were measured. The Configuration cores were 22.86-cm and 45.72-cm square and were reflected with 8.1 3-cm and 10.1 6-cm thick side polyethylene reflectors, respectively. The configurations had 10.1 6-cm thick top and bottom polyethylene reflectors. For some configurations, the Rossi-a, which is an eigenvalue value characteristic for a particular configuration, was m… more
Date: January 1, 2002
Creator: Sanchez, R. G. (Rene G.); Loaiza, D. J. (David J.) & Kimpland, R. H. (Robert H.)
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Fuel System Compatibility Issues for Prometheus-1

Description: Compatibility issues for the Prometheus-1 fuel system have been reviewed based upon the selection of UO{sub 2} as the reference fuel material. In particular, the potential for limiting effects due to fuel- or fission product-component (cladding, liner, spring, etc) chemical interactions and clad-liner interactions have been evaluated. For UO{sub 2}-based fuels, fuel-component interactions are not expected to significantly limit performance. However, based upon the selection of component materia… more
Date: January 20, 2006
Creator: Noe, DC; Gibbard, KB & Krohn, MH
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Dynamic reponse of a cylindrical shell immersed in a potential fluid

Description: A numerical solution technique is presented for determining the dynamic response of a thin, elastic, circular, cylindrical shell of constant wall thickness and density, immersed in a potential fluid. The shell may be excited by an arbitrary radial forcing function with a specified time history and spatial distribution. In addition, a pressure history may be specified over a segment of the fluid outer boundary. Any of the natural shell end conditions may be prescribed. A numerical instability pr… more
Date: April 18, 1978
Creator: Cummings, G. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

The Emma Commissioning Procedure

Description: The author begins with a brief review of the goals of the EMMA experiment. He then describe two stages of EMMA commissioning. The first stage is simply to get the beam to circulate a full turn in the ring, and is done only once during the course of the experiment. The second stage will be repeated several times, at least once for each lattice configuration, and involves two parts: setting the required values for the machine parameters, and determining the tunes and time of flight as a function … more
Date: November 5, 2007
Creator: Berg, J. S.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Conversion and Evaluation of the University of Massachusetts Lowell Research Reactor From High-Enriched To Low-Enriched Uranium Fuel

Description: The process for converting the University of Massachusetts Lowell Research Reactor (UMLRR) from high-enrichment uranium (HEU) fuel to low-enrichment uranium (LEU) fuel began in 1988. Several years of design reviews, computational modeling, and thermal hydraulic analyses resulted in a preliminary reference core design and configuration based on 20 standard, MTR-type, flat-plate, 19.75% enriched, uranium silicide (u3Si2) fuel elements. A final safety analysis for the fuel conversion was submitted… more
Date: November 19, 2003
Creator: Bobek, Leo M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

MONTE-CARLO BURNUP CALCULATION UNCERTAINTY QUANTIFICATION AND PROPAGATION DETERMINATION

Description: MONTEBURNS is a Monte-Carlo depletion routine utilizing MCNP and ORIGEN 2.2. Uncertainties exist in the MCNP transport calculation, but this information is not passed to the depletion calculation in ORIGEN or saved. To quantify this transport uncertainty and determine how it propagates between burnup steps, a statistical analysis of a multiple repeated depletion runs is performed. The reactor model chosen is the Oak Ridge Research Reactor (ORR) in a single assembly, infinite lattice configurati… more
Date: May 8, 2011
Creator: Nichols, T.; Sternat, M. & Charlton, W.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Design guide for calculating hydrodynamic mass. Part I. Circular cylindrical structures

Description: Many reactor and plant components contain, or are submerged in, a fluid. The fluid moving with a vibrating structure has an important effect on the dynamics of the structure, particularly on its natural frequencies. The effect of the fluid on natural frequencies can be accounted for using the hydrodynamic mass associated with the structure. The design guide provides formulas, graphs, and computer programs for calculating hydrodynamic masses of circular cylindrical structures.
Date: June 1, 1976
Creator: Chen, S. S. & Chung, H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

NERI PROJECT 99-119."A NEW PARADIGM FOR AUTOMATIC DEVELOPMENT OF HIGHLY RELIABLE CONTROL ARCHITECTURES FOR NUCLEAR POWER PLANTS."PHASE-1 PROGRESS REPORT

Description: This report describes the tasks performed and the progress made during Phase 1 of the DOE-NERI project number 99-119 entitled ''Automatic Development of Highly Reliable Control Architecture for Future Nuclear Power Plants''. This project is a collaboration effort between the Oak Ridge National Laboratory (ORNL,) The University of Tennessee, Knoxville (UTK) and the North Carolina State University (NCSU). ORNL is the lead organization and is responsible for the coordination and integration of all… more
Date: August 29, 2000
Creator: March-Leuba, J.A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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