50 Matching Results

Search Results

Results: 1 - 24 next
open access

End-of-life destructive examination of light water breeder reactor fuel rods

Description: Destructive examination of 12 representative Light Water Breeder Reactor fuel rods was performed following successful operation in the Shippingport Atomic Power Station for 29,047 effective full power hours, about five years. Light Water Breeder Reactor fuel rods were unique in that the thorium oxide and uranium-233 oxide fuel was contained within Zircaloy-4 cladding. Destructive examinations included analysis of released fission gas; chemical analysis of the fuel to determine depletion, iodine… more
Date: October 1, 1987
Creator: Richardson, K.D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Internal hydriding in irradiated defected Zircaloy fuel rods: A review

Description: Although not a problem in recent commercial power reactors, including the Shippingport Light Water Breeder Reactor, internal hydriding of Zircaloy cladding was a persistent cause of gross cladding failures during the 1960s. It occurred in the fuel rods of water-cooled nuclear power reactors that had a small cladding defect. This report summarizes the experimental findings, causes, mechanisms, and methods of minimizing internal hydriding in defected Zircaloy-clad fuel rods. Irradiation test data… more
Date: October 1, 1987
Creator: Clayton, J C
Item Type: Refine your search to only Report
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
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Shippingport operations with the Light Water Breeder Reactor core.

Description: This report describes the operation of the Shippingport Atomic Power Station during the LWBR (Light Water Breeder Reactor) Core lifetime. It also summarizes the plant-oriented operations during the period preceding LWBR startup, which include the defueling of The Pressurized Water Reactor Core 2 (PWR-2) and the installation of the LWBR Core, and the operations associated with the defueling of LWBR. The intent of this report is to examine LWBR experience in retrospect and present pertinent and s… more
Date: March 1, 1986
Creator: Budd, W. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Cladding corrosion and hydriding in irradiated defected zircaloy fuel rods

Description: Twenty-one LWBR irradiation test rods containing ThO/sub 2/-UO/sub 2/ fuel and Zircaloy cladding with holes or cracks operated successfully. Zircaloy cladding corrosion on the inside and outside diameter surfaces and hydrogen pickup in the cladding were measured. The observed outer surface Zircaloy cladding corrosion oxide thicknesses of the test rods were similar to thicknesses measured for nondefected irradiation test rods. An analysis model, which was developed to calculate outer surface oxi… more
Date: August 1985
Creator: Clayton, J. C.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Installation of the Light-Water Breeder Reactor at the Shippingport Atomic Power Station

Description: This report summarizes the refueling operations performed to install a Light Water Breeder Reactor (LWBR) core into the existing pressurized water reactor vessel at the Shippingport Atomic Power Station. Detailed descriptions of the major installation operations (e.g., primary system preconditioning, fuel installation, pressure boundary seal welding) are included as appendices to this report; these operations are of technical interest to any reactor servicing operation, whether the reactor is a… more
Date: May 1, 1983
Creator: Massimino, R.J. & Williams, D.A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Design features of the Light Water Breeder Reactor (LWBR) which improve fuel utilization in light water reactors

Description: This report surveys reactor core design features of the Light Water Breeder Reactor which make possible improved fuel utilization in light water reactor systems and breeding with the uranium-thorium fuel cycle. The impact of developing the uranium-thorium fuel cycle on utilization of nuclear fuel resources is discussed. The specific core design features related to improved fuel utilization and breeding which have been implemented in the Shippingport LWBR core are presented. These design feature… more
Date: August 1981
Creator: Hecker, H. C. & Freeman, L .B.
Item Type: Refine your search to only Report
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.)
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Model for incorporating fuel swelling and clad shrinkage effects in diffusion theory calculations

Description: A model has been devised for incorporating into the thermal feedback procedure of the PDQ few-group diffusion theory computer program the explicit calculation of depletion and temperature dependent fuel-rod shrinkage and swelling at each mesh point. The model determines the effect on reactivity of the change in hydrogen concentration caused by the variation in coolant channel area as the rods contract and expand. The calculation of fuel temperature, and hence of Doppler-broadened cross sections… more
Date: March 1, 1980
Creator: Schick, W.C. Jr.; Milani, S. & Duncombe, E.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Determination of statistically based design limits associated with engineering models.

Description: This report provides a usable reference of methods and procedures for the construction of both one-sided and two-sided ..gamma../P statistical tolerance limits for design application to both linear and nonlinear models in any number of variables.
Date: February 1, 1980
Creator: Ginsburg, H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Out-of-pile hydriding and thermal relaxation of reactor fasteners using Zircaloy components: the REM-120 test.

Description: Six different fastened joints representing the various combinations of materials in contact with Zircaloy in the Light Water Breeder Reactor (LWBR) were tested in 520/sup 0/F water for 60 days to determine the out-of-pile hydriding tendencies of the Zircaloy components in the joints. No evidence of massive, accelerated hydriding was found in this test although other testing has shown that local hydriding can occur in one of the fasteners. The same six fastener designs were tested in 600/sup 0/F… more
Date: January 1, 1980
Creator: Duenkel, D.A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Fuel rod-grid interaction wear: in-reactor tests

Description: Wear of the Zircaloy cladding of LWBR irradiation test fuel rods, resulting from relative motion between rod and rod support contacts, is reported. Measured wear depths were small, 0.0 to 2.7 mils, but are important in fuel element behavior assessment because of the local loss of cladding thickness, as well as the effect on grid spring forces that laterally restrain the rods. An empirical wear analysis model, based on out-of-pile tests, is presented. The model was used to calculate the wear on … more
Date: November 1, 1979
Creator: Stackhouse, R. M.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Thoria powder process development

Description: The development program to identify the critical parameters for the process of converting thorium nitrate solution into thoria powder is described. Thorium oxalate hexahydrate is precipitated from the reaction of thorium nitrate solution with oxalic acid. The resulting thorium oxalate hexahydrate slurry is filter pressed into a cake which is air calcined to form thoria powder. Changes in the critical processing parameters such as free nitric acid content of the thorium nitrate solution, precipi… more
Date: October 1, 1979
Creator: Hutchison, C.R. & Lloyd, R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

FLASH6 simulation of semiscale blowdown data, NRC Standard Problems 2 and 3

Description: FLASH6 computer program calculations are compared with experimental data from two simulated loss-of-coolant accident blowdown tests which are designated as numbers 2 and 3 in the Standard problem Series sponsored by the Nuclear Regulatory Commission for reactor safety assessment. Both tests are isothermal blowdowns smulating a double-ended, cold-leg break and were conducted in the electrically-heated, 1-1/2 Loop Semiscale System at Idaho National Engineering Laboratory. The blowdown tests were … more
Date: September 1, 1979
Creator: Harris, B.D.; Prelewicz, D.A. & Beus, S.G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Effect of simulated thermal shield motion on nuclear instrument response: measurements and calculations

Description: An experiment has been performed to determine the effect of motion of a thermal shield on the neutron signal expected from ex-core detectors. Using a mockup of the LWBR reactor vessel, thermal shield, and core barrel in conjunction with a /sup 252/Cf neutron source, the change in detector signal with displacement of the various components was investigated. It was found that moving the thermal shield would produce a significant change in detector signal, although the effect was smaller than woul… more
Date: August 1, 1979
Creator: Schick, W. C., Jr.; Emert, C. J.; Shure, K. & Natelson, M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

AIRWAY: a fortran computer program to estimate radiation dose commitments to man from the atmospheric release of radionuclides

Description: The AIRWAY computer program was developed to estimate the radiation dose commitments accured by all the people affected by the atmospheric release of radionuclides from a nuclear facility. This computer program provides dose commitment estimates for people on the boundary of the facility, in the immediate vicinity (i.e., within 80 to 100 km) and in the portios of the world beyond the immediate vicinity which are affected by the release. The AIRWAY program considers dose commitments resulting fr… more
Date: June 1979
Creator: Rider, J. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Nondestructive assay of UO/sub 2/--ThO/sub 2/ fuel pellets using the delayed neutron pellet assay gage

Description: This report describes the use of a delayed neutron pellet assay gage to determine nondestructively the fissile content of fuel pellets during the manufacture of the Light Water Breeder Reactor (LWBR) core. The gage characteristics are described including the nature of the calibration curves and the gage sensitivities to pellet parameters. Statistical methods are derived for analyzing the data to obtain the mean weight percent of total uranium in each blend of fuel material as well as the loadin… more
Date: June 1, 1979
Creator: Emert, C.J.; Milani, S. & Beggs, W.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Results of initial nuclear tests on LWBR

Description: This report presents and discusses the results of physics tests performed at beginning of life on the Light Water Breeder Reactor (LWBR). These tests have confirmed that movable seed assembly critical positions and reactivity worths, temperature coefficients, xenon transient characteristics, core symmetry, and core shutdown are within the range of values used in the design of the LWBR and its reactor protection analysis. Measured core physics parameters were found to be in good agreement with t… more
Date: June 1, 1979
Creator: Sarber, W. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
Back to Top of Screen