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Low strain diameter expansion of internally pressurized Zircaloy-4 tubing at high temperatures

Description: Tests of closed-end, internally pressurized, Zircaloy-4 tubing specimens were utilized to develop low strain creep characteristics as a function of time at temperatures in the range of 1475/sup 0/F to 2000/sup 0/F (802/sup 0/C to 1093/sup 0/C) and hoop stresses in the range of 250 to 2500 psi for use in loss-of-coolant accident (LOCA) analyses. The strain rate above the start of the alpha to beta phase transformation region, approximately 1490/sup 0/F (810/sup 0/C), was found to be sensitive to… more
Date: March 1978
Creator: White, L.S. & Busby, C.C.
Partner: UNT Libraries Government Documents Department
open access

Susceptibility of unirradiated recrystallized Zircaloy-4 tubing to stress corrosion cracking

Description: Stress corrosion cracking (SCC) in unirradiated recrystallized Zircaloy-4 internally pressurized tubing specimens in atmospheres containing iodine vapor, cesium, or combinations of iodine and cesium is evaluated experimentally in terms of the effects of internal surface flaw morphology, iodine and cesium concentrations, tubing hydrogen content, test temperature, and test atmosphere water vapor content on the time to failure. The iodine vapor SCC data are analyzed in the framework of a fracture … more
Date: December 1977
Creator: Polan, N. W. & Tucker, R. P.
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.
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.
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.
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.
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.
Partner: UNT Libraries Government Documents Department
open access

Effect of fuel chips on cladding stress in zircaloy clad oxide fuel rods

Description: Zircaloy clad oxide fuel rods are subjected to a variety of core power transients. One of these, an up-power transient, can place a severe burden on the fuel rod cladding that would potentially lead to rupture if not properly allowed for during the fuel rod design and plant operation. The cladding stress during such a transient can be increased by the presence of fuel chips between the oxide fuel pellet and the cladding. An analysis procedure based on mechanical tests of fuel and cladding was d… more
Date: November 1978
Creator: Yerman, J. F.
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.
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.
Partner: UNT Libraries Government Documents Department
open access

Corrosion of Zircaloy-4 tubing in 68OF water

Description: Seamless Zircaloy-4 tubing is utilized as fuel rod cladding in light water reactors. Water corrosion tests at 68OF have been performed to determine the corrosion and hydriding characteristics of Zircaloy-4 tubing, fabricated by cold reduction and finished in two metallurgical conditions: a stress-relief anneal (SRA) and a recrystallization anneal (RXA). These corrosion tests revealed differences in the post-transition corrosion product weight gains of the two materials. A computer corrosion mod… more
Date: December 1, 1978
Creator: Marino, G. P. & Fischer, R. L.
Partner: UNT Libraries Government Documents Department
open access

ASBLT: a system of DATATRAN MODULES which process core fuel loading for use in as-built calculations

Description: ASBLT is a computer program consisting of DATATRAN MODULES which was used during the manufacturing phase of LWBR to collect and evaluate as-built data. The program was part of the LWBR fuel rod inspection process and produced sections of module assembly certification reports. ASBLT used fuel pellet, fuel rod and module assembly data to compute core inventories and to supply input to nuclear design programs for as-built core calculations.
Date: February 1, 1979
Creator: Beaudoin, B.R.; Beggs, W.J.; Case, C.R. & Wilczynski, R.
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.
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.
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.
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.
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.
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.
Partner: UNT Libraries Government Documents Department
open access

Iodine and cesium in oxide fuel pellets and zircaloy-4 cladding of irradiated fuel rods

Description: Measurements of fission product iodine and cesium are reported for thoria and binary (ThO/sub 2/--UO/sub 2/) fuels with various irradiation histories. These volatile fission products were measured on the cladding surface or in the fuel by using specially developed radiochemical techniques. The radiochemical iodine measurements are found to be in general agreement with a theoretical iodine release model for irradiated fuel. Microprobe examinations of irradiated fuel rod cladding sections show fi… more
Date: March 1, 1979
Creator: Ivak, D. M. & Waldman, L. A.
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.
Partner: UNT Libraries Government Documents Department
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.
Partner: UNT Libraries Government Documents Department
open access

PDQ-8 reference manual

Description: The PDQ-8 program is designed to solve the neutron diffusion, depletion problem in one, two, or three dimensions on the CDC-6600 and CDC-7600 computers. The three dimensional spatial calculation may be either explicit or discontinuous trial function synthesis. Up to five lethargy groups are permitted. The fast group treatment may be simplified P(3), and the thermal neutrons may be represented by a single group or a pair of overlapping groups. Adjoint, fixed source, one iteration, additive fixed… more
Date: May 1, 1978
Creator: Pfiefer, C J & Spitz, C J
Partner: UNT Libraries Government Documents Department
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
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