50 Matching Results

Search Results

prev Results: 25 - 48 next
open access

Critical heat flux experiments with a local hot patch in an internally heated annulus

Description: Critical heat flux experiments were conducted for upflow of water in a vertical 84 inch annular flow channel, 0.303 inch heated I.D. and 0.500 inch unheated O.D. Test data were obtained at pressures from 1200 to 2000 psia, mass velocities from 0.25 x 10/sup 6/ to 2.8 x 10/sup 6/ lb/hr-ft/sup 2/ and inlet temperatures ranging from 200 to 600/sup 0/F. Three different test sections were employed with (1) axially uniform heat flux over the 84 inch length to serve as a no-hot-patch data base, (2) ax… more
Date: February 1, 1979
Creator: Mortimore, E.P. & Beus, S.G.
Partner: UNT Libraries Government Documents Department
open access

Summary of the hydraulic evaluation of LWBR

Description: The principal hydraulic performance features of the Light Water Breeder Reactor are summarized in this report. The calculational models and procedures used for prediction of reactor flow and pressure distributions under steady-state and transient operating conditions are described. Likewise, the analysis models for evaluation of the static and dynamic performance characteristics of the hydraulically-balanced and hydraulically-buffered movable-fuel reactivity-control system are outlined. An exte… more
Date: April 1, 1981
Creator: Stout, J.W.; Lerner, S.; McWilliams, K.D. & Turner, J.R. (eds.)
Partner: UNT Libraries Government Documents Department
open access

Fission gas release from ThO/sub 2/ and ThO/sub 2/--UO/sub 2/ fuels

Description: Fission gas release data are presented from 51 fuel rods irradiated as part of the LWBR irradiations test program. The fuel rods were Zircaloy-4 clad and contained ThO/sub 2/ or ThO/sub 2/-UO/sub 2/ fuel pellets, with UO/sub 2/ compositions ranging from 2.0 to 24.7 weight percent and fuel densities ranging from 77.8 to 98.7 percent of theoretical. Rod diameters ranged from 0.25 to 0.71 inches and fuel active lengths ranged from 3 to 84 inches. Peak linear power outputs ranged from 2 to 22 kw/ft… more
Date: August 1, 1978
Creator: Goldberg, I.; Spahr, G. L.; White, L. S.; Waldman, L. A.; Giovengo, J. F.; Pfennigwerth, P. L. et al.
Partner: UNT Libraries Government Documents Department
open access

Water cooled breeder program summary report

Description: The purpose of the Department of Energy Water Cooled Breeder Program was to demonstrate pratical breeding in a uranium-233/thorium fueled core while producing electrical energy in a commercial water reactor generating station. A demonstration Light Water Breeder Reactor (LWBR) was successfully operated for more than 29,000 effective full power hours in the Shippingport Atomic Power Station. The reactor operated with an availability factor of 76% and had a gross electrical output of 2,128,943,47… more
Date: October 1, 1987
Partner: UNT Libraries Government Documents Department
open access

FLASH-6: simulation of top injection emergency core cooling heat transfer tests

Description: Data from top injection ECCS tests conducted at Columbia University have been analyzed as part of an effort to qualify the FLASH-6 computer program for performing post-blowdown heat transfer calculations for the LWBR Safety Analysis. These experiments, which employed a full-scale fuel assembly with electrical heater rods to simulate an inlet rupture for a pressurized water reactor, provided test conditions and rod cooling mechanisms quite similar to those encountered in the postulated LWBR cold… more
Date: May 1, 1977
Creator: Lincoln, F. W.
Partner: UNT Libraries Government Documents Department
open access

Model to estimate the local radiation doses to man from the atmospheric release of radionuclides

Description: A model was developed to estimate the radiation dose commitments received by people in the vicinity of a facility that releases radionuclides into the atmosphere. This model considers dose commitments resulting from immersion in the plume, ingestion of contaminated food, inhalation of gaseous and suspended radioactivity, and exposure to ground deposits. The dose commitments from each of these pathways is explicitly considered for each radionuclide released into the atmosphere and for each daugh… more
Date: April 1, 1977
Creator: Rider, J. L. & Beal, S. K.
Partner: UNT Libraries Government Documents Department
open access

Measurement of the thorium absorption cross section shape near thermal energy

Description: The shape of the thorium absorption cross section near thermal energies was investigated. This shape is dominated by one or more negative energy resonances whose parameters are not directly known, but must be inferred from higher energy data. Since the integral quantity most conveniently describing the thermal cross section shape is the Westcottg-factor, effort was directed toward establishing this quantity to high precision. Three nearly independent g-factor estimates were obtained from measur… more
Date: November 1, 1976
Creator: Green, L.
Partner: UNT Libraries Government Documents Department
open access

Monte Carlo simulation using the meter system with application related to LWBR

Description: METER is a Monte Carlo computer program which can be used to simulate the interaction between independent random variables and their effects on one or more dependent random variables. The program is easy to use for simple simulations but is capable of accommodating complex simulations. METER processes input, generates random numbers from several common frequency distributions under user control, performs the simulation which the user has coded in FORTRAN, and displays results.
Date: February 1, 1977
Creator: Beaudoin, B. R.
Partner: UNT Libraries Government Documents Department
open access

Model to estimate radiation dose commitments to the world population from the atmospheric release of radionuclides

Description: The equations developed for use in the LWBR environmental statement to estimate the dose commitment over a given time interval to a given organ of the population in the entire region affected by the atmospheric releases of a radionuclide are presented and may be used for any assessment of dose commitments in these regions. These equations define the dose commitments to the world resulting from a released radionuclide and each of its daughters and the sum of these dose commitments provides the t… more
Date: February 1978
Creator: Rider, J.L. & Beal, S.K.
Partner: UNT Libraries Government Documents Department
open access

Forces in bolted joints: analysis methods and test results utilized for nuclear core applications

Description: Analytical methods and test data employed in the core design of bolted joints for the LWBR core are presented. The effects of external working loads, thermal expansion, and material stress relaxation are considered in the formulation developed to analyze joint performance. Extensions of these methods are also provided for bolted joints having both axial and bending flexibilities, and for the effect of plastic deformation on internal forces developed in a bolted joint. Design applications are il… more
Date: March 1, 1981
Creator: Crescimanno, P. J. & Keller, K. L.
Partner: UNT Libraries Government Documents Department
open access

Uranium-233 purification and conversion to stabilized ceramic grade urania for LWBR fuel fabrication

Description: High purity ceramic grade urania (/sup 233/UO/sub 2/) used in manufacturing the fuel for the Light Water Breeder Reactor (LWBR) core was made from uranium-233 that was obtained by irradiating thoria under special conditions to result in not more than 10 ppM of uranium-232 in the recovered uranium-233 product. A developmental study established the operating parameters of the conversion process for transforming the uranium-233 into urania powder with the appropriate chemical and physical attribut… more
Date: October 1, 1980
Creator: Lloyd, R.
Partner: UNT Libraries Government Documents Department
open access

Calculational model used in the analysis of nuclear performance of the Light Water Breeder Reactor (LWBR)

Description: The calculational model used in the analysis of LWBR nuclear performance is described. The model was used to analyze the as-built core and predict core nuclear performance prior to core operation. The qualification of the nuclear model using experiments and calculational standards is described. Features of the model include: an automated system of processing manufacturing data; an extensively analyzed nuclear data library; an accurate resonance integral calculation; space-energy corrections to … more
Date: August 1978
Creator: Freeman, L. B.
Partner: UNT Libraries Government Documents Department
open access

Development and control of the process for the manufacture of zircaloy-4 tubing for LWBR fuel rods

Description: The technical requirements for the Light Water Breeder Reactor (LWBR) fuel elements (fuel rods) imposed certain unique requirements for the low hafnium Zircaloy-4 tubing used as fuel rod cladding. This report describes, in detail, the tube manufacturing process, the product and process controls used, the inspections and tests performed, and the efforts involved in refining a commercial tube reducing process to produce tubes that would satisfy the requirements for LWBR fuel rod cladding.
Date: January 1, 1981
Creator: Eyler, J.H.
Partner: UNT Libraries Government Documents Department
open access

Pressure pulse test results and qualification of the FLASH-34 flexible structural member model with a surge tank attached to the test vessel

Description: Pressure pulse tests were conducted with both solid and flexible test sections installed in a test vessel filled with room temperature water. A surge tank whose volume was approximately equal to that of the test vessel with the test section installed was connected to the test vessel by a /sup 1///sub 8/ inch I.D., 8 inch long surge line. Pressure pulses of magnitude up to 1275 psid and durations from 4.6 to 55.8 msec were generated in the test vessel with a drop hammer and piston pulse generato… more
Date: August 1, 1977
Creator: Schwirian, R. E.
Partner: UNT Libraries Government Documents Department
open access

Ex-reactor deformation of externally pressurized short lengths of fuel rod cladding.

Description: The DECAG (Deformation of Cladding into Axial Gaps) ex-reactor test program evaluated deformation of Zircaloy-4 cladding into axial gaps in tubular fuel elements. These axial gaps are the result of cladding elongation and fuel stack shrinkage. The test program consisted of twelve series and subseries of both fully recrystallized and stress-relieved highly cold worked tubing tested under pressure-temperature combinations in autoclaves. The test program also verified the validity of achieving tes… more
Date: May 1, 1979
Creator: Selsley, I. A.
Partner: UNT Libraries Government Documents Department
open access

Out-of-pile accelerated hydriding of Zircaloy fasteners

Description: Mechanical joints between Zircaloy and nickel-bearing alloys, mainly the Zircaloy-4/Inconel-600 combination, were exposed to water at 450/sup 0/F and 520/sup 0/F to study hydriding of Zircaloy in contact with a dissimilar metal. Accelerated hydriding of the Zircaloy occurred at both temperatures. At 450/sup 0/F the dissolved hydrogen level of the water was over ten times that at 520/sup 0/F. At 520/sup 0/F the initially high hydrogen ingress rate decreased rapidly as exposure time increased and… more
Date: October 1, 1979
Creator: Clayton, J. C.
Partner: UNT Libraries Government Documents Department
open access

Sources of internal hydriding in unirradiated thoria-fueled Zircaloy rods

Description: The low-temperature (less than or equal to 550/sup 0/C), low-pressure (less than or equal to 36 torr) hydrogen absorption characteristics of specific types of Zircaloy-4 internal cladding surfaces (pickled, machined and welded) were investigated. The highest hydrogen contents were found at the machined and abraded surfaces. Although the pickled surface film on Zircaloy-4 retarded hydrogen pickup, especially at lower temperatures (less than or equal to 400/sup 0/C) and very low hydrogen pressure… more
Date: February 1, 1979
Creator: Clayton, J. C.
Partner: UNT Libraries Government Documents Department
open access

Nuclear analysis and performance of the Light Water Breeder Reactor (LWBR) core power operation at Shippingport

Description: This report presents the nuclear analysis and discusses the performance of the LWBR core at Shippingport during power operation from initial startup through end-of-life at 28,730 EFPH. Core follow depletion calculations confirmed that the reactivity bias and power distributions were well within the uncertainty allowances used in the design and safety analysis of LWBR. The magnitude of the core follow reactivity bias has shown that the calculational models used can predict the behavior of U/sup … more
Date: April 1, 1984
Creator: Hecker, H. C.
Partner: UNT Libraries Government Documents Department
open access

Summary of the nuclear design and performance of the Light Water Breeder Reactor (LWBR)

Description: This report presents a summary of the nuclear design and expected nuclear performance of the Light Water Breeder Reactor during operation at the Shippingport Atomic Power Station. Performance predictions are presented for core lifetime, breeding margin, power distributions and performance, kinetic and stability parameters, and for core shutdown and reactivity control capability. Also included is a summary of as-built dimensions of core components and of development of breeding parameter equatio… more
Date: June 1, 1979
Creator: Hecker, H. C.
Partner: UNT Libraries Government Documents Department
open access

Summary of the thermal evaluation of LWBR

Description: This report describes the thermal evaluation of the core for the Shippingport Light Water Breeder Reactor. This core contains unique thermal-hydraulic features such as (1) close rod-to-rod proximity, (2) an open-lattice array of fuel rods with two different diameters and rod-to-rod spacings in the same flow region, (3) triplate orifices located at both the entrance and exit of fuel modules and (4) a hydraulically-balanced movable-fuel system coupled with (5) axial-and-radial fuel zoning for rea… more
Date: March 1, 1980
Creator: Lerner, S.; McWilliams, K. D.; Stout, J. W. & Turner, J. R.
Partner: UNT Libraries Government Documents Department
open access

Summary of several hydraulic tests in support of the light water breeder reactor design

Description: As part of the Light Water Breeder Reactor development program, hydraulic tests of reactor components were performed. This report presents the results of several of those tests performed for components which are somewhat unique in their application to a pressurized water reactor design. The components tested include: triplate orifices used for flow distribution purposes, multiventuri type flowmeters, tight lattice triangular pitch rod support grids, fuel rod end support plates, and the balance … more
Date: May 1, 1979
Creator: McWilliams, K. D. & Turner, J. R.
Partner: UNT Libraries Government Documents Department
open access

Properties of thoria and thoria-urania: a review

Description: Information on the physical, chemical, and mechanical properties of thoria and thoria-urania is reviewed and assessed. The properties discussed are those judged to be important for an understanding of the behavior of these oxides as nuclear fuel materials. Evaluation was made, where possible, of the effects of composition, material variables, temperature, and irradiation exposure. Data were taken from a review of the literature and from both published and unpublished data derived from the Light… more
Date: June 1, 1978
Creator: Belle, J. & Berman, R. M.
Partner: UNT Libraries Government Documents Department
open access

Methods for assessing homogeneity in ThO/sub 2/--UO/sub 2/ fuels

Description: ThO/sub 2/-UO/sub 2/ solid solutions fabricated as LWBR fuel pellets are examined for uniform uranium distribution by means of autoradiography. Kodak NTA plates are used. Images of inhomogeneities are 29 +- 10 microns larger in diameter than the high-urania segregations that caused them, due to the range of alpha particles in the emulsion, and an appropriate correction must be made. Photographic density is approximately linear with urania content in the region between underexposure and overexpo… more
Date: June 1, 1978
Creator: Berman, R. M.
Partner: UNT Libraries Government Documents Department
Back to Top of Screen