Hanford fuel elements are made by brazing uranium cores in aluminum cans. The interface, or junction, between the AlSi braze and uranium core known as the compound layer, is composed of an intermetallic complex. The properties of this compound layer, brittleness, ductility, toughness, are considered to have a pronounced influence on the performance of fuel elements in the reactors. This report presents the results of initial efforts to identify the compound layers and establish some of the process conditions and variables which influence the properties of the compound layer, in particular, the lead preheat time.

Graphite shrinkage of 0.60 inches (approximately 30 per cent) has been observed at F Reactor in the region of maximum graphite distortion. A reduction of graphite distortion at B Reactor of 0.60 inches in the top-center and 0.32 inches in the top-far region also has been observed. Analysis of the vertical traverse data indicates that continued graphite annealing with resultant decrease in graphite distortion might be anticipated although perhaps at a reduced rate. No significant detrimental effects have been observed from operation with either the increased charge length or the flux slightly skewed to the front of the reactor. Operation with severe flux skewing resulted in detrimental control effects. It is recommended that operation with the flux skewed to the front of B and F Reactors through the use of a longer charge (centered slightly upstream of the graphite century-line) be continued subject to periodic review.

The cost and feasibility of blending UNH streams of different uranium enrichments at HAPO was evaluated on a preliminary basis. Cases studied were blending 37.5% enriched UNH with depleted E metal UNH to yield a 0.947% enriched end product, and blending depleted E metal UNH with the depleted natural uranium to yield 0.7115% enriched end product. A reasonable degree of feasibility is indicated for such a blend program at HAPO.

The kinetics of the gamma deg C was con- beta deg C was con- alpha , beta deg C was con- gamma , and alpha deg C was con- beta deg C was con- gamma transformations were determined with a fiuid displacement technique. The rates of formation of the alpha and beta phases from the gamma phase were determined after gamma heat treating and allowing a sample to traasform isothermally in the alpha and beta ramges. Isothermal reaction curves were obtained from 160 C to -78C. The time-temperature-transformation curve of the gamma deg C was con- beta deg C was con- alpha transformation was plotted. The effect of the gamma heat treating time and temperature on the rate of transformation was examined. Isothermal reaction curves and time-temperature- transformation curves of the beta deg C was con- gamma , and alpha deg C was con- beta deg C was con- gamma transformations were plotted. Photomicrographs of specimens having transformed from the gamma range at different rates of transformation are presented. (auth)

The design and constructlon of the shielding facility at Battelle are described. This facility consists of an open pool with a fission plate, an instrument bridge and tower, a control room, and radiation-detection instruments. The shielding pool is located at the end of the thermal column of the Battelle Research Reactor (BRR). The fission plate is 28 in. in diameter and contains approximately 3.5 kg of U/sup 235/. The plate was fabricated from three pieces of highly enriched U and clad with about 25 mils of 2S Al. It generates about 24 w during steady-state reactor operation. The fission spectra of neutrons and gamma rays produced by the fission plate are free from appreclible background radiations. The ratio of thermal to epithermal neutrons impinging upon the fission plate is approximately 67, indicating a low fast-neutron background. Assuming an average energy of 2 Mev for backgrounnd gamma rays results in a ratio of thermal-neutron flux to gamma flux of 16. (auth)

Air-flow studies were run in a quarter-scale flow model of the PWR to determine distribution of flow throughout the upper-plenum region with two different hold-down-barrel designs. With each hold-down barrel, flow paths were determined for operation with four loops, three loops, two opposed loops, and two adjacent loops. Exploration of flow patterns and velocities throughout the upper plenum showed that circulation of coolant throughout the upper plenum was satisfactory with either of the hold-down barrels investigated. (auth)

None

Metullographic examinations of representative reactor components and coupons from HRP in-pile loop L-2-l7 are reported. The loop operated for a total of 1l36.8 hours at 300 deg C in beam hole HB-2 of the LITR. The results are discussed and tabulated. Photographs are also included. (J.R.D.)

The study of the Oak Ridge School of Reactor Technology Buttermilk Reactor is continued with analog computer simulation of a loss of fuel flow incident. (T-R-H-)

The cause and significance of the changes in chemical composition of the HRT fuel and changes in reactivity during operation, particularly in run 17A, were investigated. It was concluded that a rise in reactor power level causes deposition of U, Cu, and Ni in some hydrolytic process within the core circulation system in a region which is at a position between zero and average nuclear importance. The deposition requires several minutes to several hours and is relatively easily reversiable when the power is lowered. (J.R.D.)

The results of the Stanford Research Institute studies of the effects of radiation on solvent extraction processes are summarized, and a desirable direction for future work is indicated. Studies performed to date have shown that: (1) nearly all of the irradiation-induced increase in time required for TBP- -Amsco--aqueous phase separation is due to formation of a polymer, of unknown chemical structure; (2) uranium retention by the TBP-- Amsco phase during stripping operations is due approximately 65% to dibutyl phosphate and 20% to the polymer; (3) each 100 ev of energy absorbed forms abeut 0.5 hydrocarbon double bonds, with which fission product iodine could readily react; (4) dibulyl phenylphosphonate is about six times as resistant, and dibutyl butylphosphonate is twice as resistant, to radiation damage as is tribulyl phosphate. (auth)

None

The experimental system used in the determination of turbulent forced- convection heat-transfer coeificients with molten salts is described, and the results of the experimental program are detailed. The salts studied have been the mixtures NaNO/sub 2/-NaNO/sub 3/--KHO/sub 3/, LiF --NaF --KF and s with the LiF--NaF-KF mixture in Inconel tubes are explained in terms of an interfacial film. A nonwetting phenomenon is postulated to describe the decreased heat transfer in the NaF--ZrF/sub 4/-UF/sub 4/ system. The advantages of molten salts as coolants are briefly discussed. lt can be concluded that molten salts behave, in general, as ordinary fluids (0.5 < N/sub pr/ < 100) as far as heat transfer is concerned. An analysis has shown that the molten salts compare favorably with the liquid metals as reactor coolants. (auth)

S>Optical tooling has been evaluated for the measurement of physical dimensions of radioactive parts through hot cell windows. Instruments were set up outside of a four foot thick lead glass window and by means of a grid plate which had been accurately scribed, a ''contour map'' or calibration chart of the window variations was recorded. Although the window was not specially selected, the readings were within 1.0% of the true dimension without using correction factors. One of the calibration chart with the window reduced the error to plus or minus 0.1%. The method is considered feasible and sufficiently fast for a wide variety of hot cell measurements. A pin point light source is suggested as a simple check for selective assembly of lead glass laminates during manufacture of hot cell windows to provide control of optical properties. (auth)

In the studies of the dissolution of uranium -zirconium

The Homogeneous Reactor Test is designed for maintenance to be performed while the parts of the reactor are partinlly or completely submerged in water to reduce radiation levels. Tools with long handles permit the operator, standing above the equipment, to disconnect flanged joints, air lines, electrical and instrument leads, etc., in a minimum time. The techniques and tools employed to accomplish these various operations and to minimize intermixing of the contaminated process fluids with the shielding water are described. Estimates of shutdown times and costs of tools and spare parts are presented also. (auth)

A small, laboratory-sized loop was designed for steady-state radiolytic gas recombination studies. It consists of an electrolysis cell, which simulates the radiolytic gas formed in a reactor, and a bomb for containing slurry under test. The electrolysis capacity of the system is adequate for the study of slurries having recombination rates as high as 10 moles/hr/liter of slurry at the proposed slurry reactor operating conditions. (auth)

S>A proposal is presented to design, construct, and operate a thermal gradient mass transfer loop to provide data on rates of solution and deposition as functions of time. Operation of the hot solution zone under controlled isothermal conditions is planned. It is felt that data obtained in such a loop would be of value in assessing the validity of presently proposed mecharisms for thermal gradient transfer or in devising new ones. The thermal and forced convection loops appear to offer moat promise of yielding significant results. Descriptions of the proposed metal systems to be studied are given along with the experimental procedure and method of data analysis. (J.R.D.)

The integrity and suitability of 35 vol.% U/sub 3/ O/sub 8/ dispersion in Al as a fuel for foreign reactors were determined. The fuel was exposed in the beryllium reflector of the MTR. Sample fabrication and conditions of exposurne are described, and the results are tabulated. (J.R.D.)

A number of cases were studied to determine some of the nuclear characterlstics of double-blanket reactors. The reactor geometry is spherical. the average temperature is 280 deg C the core ID is 4 ft and the pressure vessel ID is 9 ft in all cases. The core is contained in a 1/2-in. Zircaloy tank, while the blanket is divided into two regions by another another 1/2-in. Zircaloy shell. The region adjacent to the core is either 0.5 or 1-ft thick Comparison is made of reactors in which either the inner or outer blanket region contains 4000 g Th/liter as ThO/sub 2/ slurry in D/sub 2/O while the other blanket region holds thorium concentrations of 0, 500, or 1000 g Th/liter. The effects of introducing an 8% poison fraction into the core and 3 g U/syo 233/kg Th into the blanket are examined individually. It is found that reactivity effects are negligible if the inner blanket contains 4000 g Th/liter and settling occurs in the dilute outer region. On the other hand. for a concentrated outer blanket, large reactivity additions are to be expected on removing the thorium from the dilute inner region. Some fuel and thorium inventory reductions appear possible …

A tabular resume of the data from 37 in-pile Zircaloy-2 rocking autoclave corrosion experiments performed since August 1954 is presented. Included are data concernin,; solutions used on the specimens before and after the reactor eKposure, sample treatment prior to irradiation conditions during exposure, data on oxygen consumption and specimen weight losses, and miscellaneous data. (J.R.D.)

This document provides conclusions made concerning inlet line (pigtail) rupture effects on the Hanford reactors.

This report describes the operation of the fuels preparation department for the month of October, 1958. Manufacturing employee relations, process development, plant improvements and financial operations are described.

Chip method experiments were performed for the preparation of Th - 9 wt.% U, U - 10 wt.% Nb, and Al--16 wt.% U - 0.2 wt.% B alloys. The work on Th-9 wt.% U indicated that the technique was applicable with oniy slight impairment of mechanical properties and slight increase of oxygen content. Experiments on U-10 wt.% Nb to produce a more corrosion-resistant alloy were not successful. The potential use of the chip method in fabricating alloys with a burnable poison such as boron appeared feasible. An aluminum alloy containing 16 wt.% U and 0.2 wt.% B showed good homogeneity. The shot method was used on an alloy of Al-25 wt.% U. The homogeneity and the mechanical properties of this alloy, when extruded, were superior to those of similar alloys produced by conventional melting and casting. Preliminary work on the blending of master alloys of a burnable poison (i.e., boron) with an aluminumuranium alloy indicated the feasibility of obtaining a homogeneous alloy with good mechanlcal properties. (auth)