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KINETIC EXPERIMENTS ON WATER BOILERS-"A" CORE REPORT-PART II. ANALYSIS OF RESULTS

Description: The status of the analytic portion of the KEWB program at the time of completion of the spherical core experiments is summarized. Three computer programs were developed for use in this analytic effort. The first reassembles and smooths three decades of reactor power data read separately from oscillogram records of reactor excursions. It then computes the logarithmic derivative of the power, energy release, fuel solution temperature, and temperature compensated reactivity. The second program uti… more
Date: February 1, 1962
Creator: Dunenfeld, M. comp.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

EQUIPOISE-3: A TWO DIMENSIONAL, TWO-GROUP, NEUTRON DIFFUSION CODE FOR THE IBM-7090 COMPUTER

Description: EQUIPOISE-3 is an IBM-7090 FORTRAN programmed code for the solution of two-group, two-dimensional, neutron diffusion equations. A maximum of 2l00 mesh points may be used, and the code will solve problems in either rectangular or cylindrical geometry. Logarithmic derivative boundary conditions are allowed, and removal of neutrons from both groups is permitted. Adjoint fluxes with the associated fluxadjoint flux regional integrals may be calculated automatically if desired. A constant buckling, g… more
Date: February 21, 1962
Creator: Fowler, T.B. & Tobias, M.L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Material Buckling Measurements on Graphite-Uranium Systems at Hanford: A Summary Tabulation

Description: Measurements of material bucklings for graphite uranium systems are summarized. A comprehensive listing and guide to the original data sources is provided. Complete information on physical and nuclear properties of the lattice and the geometry of the exponential assembly is included, along with some of the auxiliary data taken. The fuel sizes vary from 0.925 to 2.5 in. in diameter for five different fuel geometries. The lattice spacings vary from 4 3/16 to 15 in. Over 300 measurements of materi… more
Date: May 1, 1961
Creator: Wood, D. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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REACTOR LABORATORY EXPERIMENTS

Description: An exposition is presented comprising a basic set of experiments in reactor physics, engineering, and technology developed by the International Institute of Nuclear Science and Engineering. Twenty-two experiments are included in a program which may be divided into groups associated with the Argonaut Reactor, the AGN-201 Reactor, and with other reactors or auxiliary equipment. (J.R.D.)
Date: August 1, 1961
Creator: Sturm, W.J. ed.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Dynamic Simulation of Multi-Pass Pressurized Water Nuclear Power Plants by Analog Computer Techniques

Description: A kinetic model of the primary loop of a multi-pass pressurized water reactor power plant is developed to evaluate, by analog computer techniques, the transient response characteristics under conditions of steam generator load and reactor control rod perturbations. Using the 2-pass 28 Mw(t) SM-2 reactor as a typical plant, transient behavior patterns are illustrated and examined for a variety of load inputs, variations in plant constants, and analog model simplifications. (auth)
Date: June 1, 1961
Creator: Brondel, J. O.
Item Type: Refine your search to only Thesis or Dissertation
Partner: UNT Libraries Government Documents Department
open access

FLUX DISTRIBUTIONS AND LEAKAGE CURRENTS FOR SRE, P-16

Description: BS>Two-group, two-region criticality calculations were made for 10 and 11 ft diameter tanks. The 10 ft tank required a core radius of 102 cm and the 11 ft tank a core radius of 95 cm for criticality. In the calculations, the fluxes were assumed to go to zero at the edge oi the graphite reflector. The fast group of the two-group calculation was broken down into 3 fast groups. The leakage out of the core and reflector for the 4 energy groups is given. (M.C.G.)
Date: January 29, 1954
Creator: Balent, R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Analysis of the Initial Nuclear Superheat Critical Experiments. Supplementary Study Related to Bonus and Nuclear Superheat Programs

Description: A critical experiment program is carried out in a configuration similar to the BONUS reactor. The results give information concerning: the effects of different boilersuperheater geometries; the reactivity changes associated with superheater voiding or flooding; power regulation between the boiler and superheater regions; epithermal transmission probabilities for B-stainless steel and Cd control rods; the power flattening characteristics; and void simulation properties. The calculational methods… more
Date: January 30, 1961
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Preliminary Results of High-Temperature Bare U$sup 235$-C Critical Assembly Measurements

Description: The influence of temperature on the critical buckling or bare graphite assemblies with various carbon-to-uranium235 molar ratios has been measured. A range from l185: 1 to 2l,690: 1 was covered, for 45 to 1205'F. Preliminary results indicate that the fractional rate of change of critical buckling with core temperature varies monotonically with C/U2as ratio by a factor of five over the factor-of-eighteen range in gross C/U2as ratio. This quantity appears to approach asymptotically a value n… more
Date: June 1, 1961
Creator: Finke, R. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Use of additional fission sources or scattering sources to model inward axial leakages in fast-reactor analysis

Description: When calculations of flux are done in less than three dimensions, bucklings are normally used to model leakages (flows) in the dimensions for which the flux is not calculated. If the net leakage for a given energy group is outward (positive), the buckling is positive, and buckling methods work well. However, if the new leakage for a given energy group is inward (negative), the buckling is negative and can lead to numerical instabilities (oscillations in the iterative flux calculation). This rep… more
Date: October 1, 1981
Creator: Grimm, K. N. & Meneghetti, D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Magnetoelastic energy calculations for finite element analysis of superconductors

Description: It has been shown that the high current density and magnetic flux density associated with superconductors can make the magnetoelastic energy a significant portion of the total energy in a structural system. The present work presents a procedure for evaluating this magnetoelastic energy for use in the finite element analysis of the structural dynamics and stability of the superconductor. A simple, special case of the element matrices is illustrated.
Date: January 1, 1977
Creator: Akin, J.E. & Stoddart, W.C.T.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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SPECTRAL SHIFT CONTROL REACTOR BASIC PHYSICS PROGRAM. EXPONENTIAL EXPERIMENTS AT ELEVATED TEMPERATURES ON LATTICES MODERATED BY D$sub 2$O-H$sub 2$O MIXTURES

Description: Results of exponential experiments conducted at elevated temperatures on rod lattices of slightly-enriched UO/sub 2/ moderated by D/sub 2/O-- H/sub 2/O mixtures are summarized. The fuel rods, 4%-enriched UO/sub 2/ swaged in stainless steel, were 0.476-inch OD by 0.016-inch wall. The non-moderator- tomoderator volume ratio was 1.006. The two moderator compositions studied were light water (0% D/sub 2/O) and a D/sub 2/O-H/sub 2/O mixture containing 81.5 mole% D/sub 2/O. The experimental facility … more
Date: March 1, 1962
Creator: Barrett, L.G.; Worsham, H.J. & Engelder, T.C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Stability of bellows used as expansion joints between superconducting magnets in accelerators

Description: For superconducting magnets, one needs many bellows for connection of various helium cooling transfer lines. There could be approximately 20,000 magnet interconnection bellows in the SSC exposed to an internal pressure. When axially compressed, internally pressurized, or insufficiently supported at their ends, bellows can become unstable, leading to gross distortion or complete failure. If several bellows are contained in a magnet assembly, failure modes might interact. If designed properly lar… more
Date: January 1, 1991
Creator: Shutt, R.P. & Rehak, M.L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Strain mapping on gold thin film buckling and siliconblistering

Description: Stress/Strain fields associated with thin film buckling induced by compressive stresses or blistering due to the presence of gas bubbles underneath single crystal surfaces are difficult to measure owing to the microscale dimensions of these structures. In this work, we show that micro Scanning X-ray diffraction is a well suited technique for mapping the strain/stress tensor of these damaged structures.
Date: September 1, 2005
Creator: Goudeau, P.; Tamura, N.; Parry, G.; Colin, J.; Coupeau, C.; Cleymand, F. et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

HANFORD DOUBLE SHELL TANK THERMAL AND SEISMIC PROJECT BUCKLING EVALUATION METHODS AND RESULTS FOR THE PRIMARY TANKS

Description: This report documents a detailed buckling evaluation of the primary tanks in the Hanford double-shell waste tanks (DSTs), which is part of a comprehensive structural review for the Double-Shell Tank Integrity Project. This work also provides information on tank integrity that specifically responds to concerns raised by the Office of Environment, Safety, and Health (ES&H) Oversight (EH-22) during a review of work performed on the double-shell tank farms and the operation of the aging waste f… more
Date: January 14, 2009
Creator: TC, MACKEY; KI, JOHNSON; JE, DEIBLER; SP, PILLI; MW, RINKER & NK, KARRI
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

HANFORD DOUBLE SHELL TANK (DST) THERMAL & SEISMIC PROJECT BUCKLING EVALUATION METHODS & RESULTS FOR THE PRIMARY TANKS

Description: This report documents a detailed buckling evaluation of the primary tanks in the Hanford double-shell waste tanks (DSTs), which is part of a comprehensive structural review for the Double-Shell Tank Integrity Project. This work also provides information on tank integrity that specifically responds to concerns raised by the Office of Environment, Safety, and Health (ES&H) Oversight (EH-22) during a review of work performed on the double-shell tank farms and the operation of the aging waste f… more
Date: February 14, 2007
Creator: TC, MACKEY; KI, JOHNSON; JE, DEIBLER; SP, PILLI; MW, RINKER & NK, KARRI
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

HANFORD DOUBLE SHELL TANK THERMAL AND SEISMIC PROJECT SUMMARY OF COMBINED THERMAL AND OPERATING LOADS WITH SEISMIC ANALYSIS

Description: This report summarizes the results of the Double-Shell Tank Thermal and Operating Loads Analysis (TaLA) combined with the Seismic Analysis. This combined analysis provides a thorough, defensible, and documented analysis that will become a part of the overall analysis of record for the Hanford double-shell tanks (DSTs). The bases of the analytical work presented herein are two ANSYS{reg_sign} finite element models that were developed to represent a bounding-case tank. The TaLA model includes the… more
Date: January 15, 2009
Creator: TC, MACKEY; JE, DEIBLER; MW, RINKER; KI, JOHNSON; FG, ABATT; NK, KARRI et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Some physics issues of carbon stripping foils

Description: Carbon foils are widely used in charge-exchange injection in high intensity hadron accelerators. There are a number of physics issues associated with the use of carbon foils, including stripping efficiency, energy deposition and foil lifetime (temperature rise, mechanical stress and buckling, etc.). This paper will give a brief discussion of these issues.
Date: June 1, 2007
Creator: Chou, W.; Lackey, J.; Tang, Z.; Yoon, P. & Kostin, M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Development of performance models for thick composites in compression

Description: This report details initial activities and results from an investigation into the failure of thick-section composite cylinders loaded in compression. The efforts are aimed at the development of models for predicting cylinder performance based on composite material strengths derived from ring and cylinder tests of unidirectional materials. Initial results indicate that existing failure theories are applicable provided that material strength allowables are based on representative tests, and that … more
Date: November 1, 1991
Creator: Blake, H. W.; Grimsby, H. J.; Starbuck, J. M. & Welch, D. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Collection and analysis of existing data for waste tank mechanistic analysis

Description: Pacific Northwest Laboratory (PNL) is conducting this study for Westinghouse Hanford Company (Westinghouse Hanford), a contractor for the US Department of Energy (DOE). The purpose of the work is to study possible mechanisms and fluid dynamics contributing to the periodic release of gases from the double-shell waste storage tanks at the Hanford Site in Richland, Washington. The waste inside the tank is generating and periodically releasing potentially flammable gases into the tank's vent system… more
Date: December 1, 1991
Creator: Allemann, R. T.; Antoniak, Z. I.; Friley, J. R.; Haines, C. E.; Liljegren, L. M. & Somasundaram, S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Structural stability analysis for the Mirror Fusion Test Facility (MFTF) jacket assembly

Description: A structural analysis was performed for the unsupported MFTF jacket assembly. The STAGS (Structural Analysis of General Shells) computer code was used to obtain linear and bifurcation buckling data for a one-quarter model considering all possible combinations of boundary conditions. The primary results are summarized.
Date: May 1, 1979
Creator: Smith, G.W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Growth of buckling instabilities during radial collapse of an impulsively-loaded cylindrical shell

Description: Conditions leading to the growth of initial imperfections for rings or cylindrical shells subjected to initial uniform inward impulsive velocity loading are investigated. The work is motivated by a need to prevent buckling of rings during the contracting ring test, which is used to determine intermediate strain rate compressive stress-strain data. A previous analysis by Abrahamson is extended to include deceleration of the ring during inward motion; and the results of this deceleration are foun… more
Date: January 1, 1987
Creator: Duffey, T. A.; Warnes, R. H. & Greene, J. M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Background cross section method as a general tool for reactor analysis

Description: The background cross section method (also called the self-shielding method) has been used extensively in fast reactor analysis. More recently it has also become important in thermal power reactor studies. This paper reviews current applications of the method and describes efforts underway at the Los Alamos Scientific Laboratory to improve the accuracy and reliability of the approach and to extend its applicability to graphite moderated systems and shielding problems. Improvements discussed incl… more
Date: January 1, 1978
Creator: MacFarlane, R. E.; Kidman, R. B.; LaBauve, R. J. & Becker, M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Nonlinear analysis of hydraulic buckling instability of ANS involute fuel plates

Description: The hydraulic buckling instability of the involute fuel plates and hydraulic coolant channels in the Advanced Neutron Source (ANS) uranium fission reactor is analyzed nonlinearly using the commercial ABAQUS finite element computer program for the fuel plates in conjunction with a user-written element for the two-dimensional fluid flow in the coolant channels. This methodology has been used for several purposes, including determination of the effect of the aluminum-clad plate plastic behavior an… more
Date: March 1, 1993
Creator: Sartory, W.K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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