The solubility of aluminum corrosion product in contact with metallic aluminum in deionized water has been determined over the range 80 to 350/sup 0/C. Evidence is presented to show that oxide dissolution results in the formation of a porous oxide on aluminum exposed in refreshed dynamic systems. Dynamic corrosion rate data have been analyzed on the basis of parabolic film growth and a linear oxide degradation process acting simultaneously on the system. The degradation process has been shown to be a function of refreshment rate.

Two new positron active isotopes, B{sup 8} and Na{sup 20}, have been found to decay to excited states of Be{sup 8} and Ne{sup 20}, which in turn decay 'instantaneously' by alpha emission. Their half-lives are 0.65 {+-} 0.1 sec. and 1/4 sec. respectively. N{sup 12} is also found to have a low energy positron group which leads to an {alpha}-unstable excited state in C{sup 12}. The masses of B{sup 8} and Na{sup 20} are 8.027 and 20.015 respectively. B{sup 8} decays by a 13.7 {+-} 0.3 Mev positron, through the same excited state of Be{sup 8} as does Li{sup 8}. Estimates of the energies of the excited state in C{sup 12} and Ne{sup 20} are made.

The conceptual design of a nuclear ram jet-rocket missile is preserved. This missile is a modified, scaled-up AC-210 nuclear ram jet carrying ammonia in the space enclosed by the spike and inlet diffuser. The payload may be a 10,000 pound thermonuclear weapon or equivalent weight of reconnaissance equipment plus local shielding as in the AC-210 missile. The payload for a missile of body size equivalent to the AC-210 will be reduced by the weight of ammonia.

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The Vernatherm unit is a temperature sensitive capsule which translates temperature change to mechanical movement of a brass plunger. A change in phase of a hydrocarbon contained in a cylinder caused by temperature change, causes movement of the brass plunger. The units are available for various temperature ranges. The adaptation considered was to monitor the outlet water temperature from individual process tubes in the ``G`` pile. The purpose of the test was to determine the magnitude of error, if any, that is induced in a standard Vernatherm unit of known calibration when subjected to gamma irradiation. The accuracy of the units prior to irradiation was within 1.25 F. An examination of the calibration curves shows that a hysteresis effect in the hydrocarbon of the unit causes the curve of descending temperature to be displaced from the ascending temperature curve. The effects of irradiation were to decrease the accuracy to within 3.75 F. After a total exposure of 17,416 {times} 10{sup 4}R at 1.1 MEV. Since the exposure of 11,441 {times} 10{sup 4}R is equivalent to approximately 2,000 months exposure in the pile at 250 MW they can conclude that the effect of radiation is not detrimental since the increase in …

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This report discusses two methods which have been considered to reduce the rear face activity. The first involves the use of a solids purge to scour out the activity, and the second employs the use of a chromic acid purge to put the activity into solution. Solids purging is found to be ineffective in reducing rear face activity levels. A chromic acid purge conducted at 60 C for 1/2 hour can be expected to reduce the Zn{sup 65} activity level about five fold without injuring the reactor or causing any harmful aftereffects.

During the history of operation of the Hanford reactors, several methods have been utilized to establish an outlet water temperature or ``Panellit`` limit based on the stability of water flowing through the process tubes. These methods have been known as ``Excess Header Pressure Limits,`` ``Trip Before Boiling Limits,`` and the most recent, ``Trip Before Instability Limits.`` Each new concept vas accepted only after considerable experimental data had proved the new method to be safe and operationally feasible. It is anticipated that in the future other tube outlet water temperature limits will be developed based on new technology. The purpose of this document is to present, in simple terms, an understandable explanation of previous operating limits, to discuss the status of the present Instability Limits, and to outline the direction of future work in raising the outlet water temperature limits.

Authorization has been received in the form of Modification No. 5 to Directive HW-158, dated March 23, 1951 to provide the necessary equipment and piping in the currently planned UO{sub 3} plant to permit the segregation of UO{sub 3} arising from the processing of stored metal waste (TBP) from that arising from ``current`` pile operation (Redox). In anticipation of this, the S Division, Manufacturing Divisions, requested that a study be made of the feasibility and cost of providing facilities for such segregation. This report is the result of that study. It concludes that by providing additional liquid storage and handling equipment, the desired segregation can be accomplished at a cost estimated to be approximately $128,000. $106,500 would be for Construction and $21,500 for Engineering. The schedule for this work will be reflected in the forthcoming modification to the C-361 Project Proposal. The general method of operation is alternately to store and process solution from TBP and Redox. The solution from TEP will be of a composition equivalent to the formula UNH and will require five days each week to process in the decomposition pots. The solution from Redox is received as 60% UNH and is batch concentrated in the storage …

For some time, it has been considered that cycling natural uranium fuel elements through the {alpha}-{beta} transformation point (approx. 662 C) is a contributing factor in split type ruptures. This hypothesis is based upon the fact that the transition temperature, a one percent increase in volume occurs. It is reasoned that as the uranium hardens under irradiation, it becomes progressively less able to adjust to the severe stresses imposed by the volume change as the material cycles through the {alpha}-{beta} transformation point. Failure finally occurs by a splitting of the core. The IPD is now interested in evaluating some of the effects of reactor operation upon fuel performance. It appears that the life of solid fuel elements may be prolonged if sudden changes in reactor operation can be minimized. It is the purpose of this report to bring to the attention of FPD management the new ideas being developed in the IPD on split type failures and to point out the effect such thinking may have on future fuel element development activities. Based on a discussion with personnel in PID, there is reasonable hope that the performance of solid fuel elements will not be limited by the {alpha}-{beta} transformation, and …

Operation, rehabilitation, and expansion of Hanford Works was undertaken by GE from Sept. 1946 to the end of 1950. As a result of engineering progress, graphite reactors continue to be the country`s primary source of plutonium in production quantities; at the end of 1950, the plutonium production rate from the Hanford reactors was 299% of the 1946 rate with a 67% increase in reactor facilities. Improvements to existing plant facilities and processes resulted in savings of $53.3 M; in addition, it would have been necessary, in order to produce the amount of Pu delivered through 1950, to have constructed facilities costing $225.4 M if the following improvements had not been made: an irradiation-stable uranium slug; annealing of graphite; increased operating power level of the reactors; and improved separation methods. Tritium production, health/safety, and community management are mentioned.

This report details activities of the Chemical Development Unit during the month of March 1954.

This document provides details of activities of the Hanford Operations Office during the month of September 1959. (FI)

This document contains information about the radiological result of a hypothetical explosion of one of the Hanford Production Reactors. Three aspects are discussed: 1. The effect of the radiation emitted from the explosion; 2. The contamination of the river and its aquatic life as a result of the fall out from the explosion; 3. The hazard which would result from humans eating contaminated fish.

A method has been adapted from ion exchange studies for removal of the fission products, Cs-137, Sr-90, and the rare earths for both untreated urine samples and the supernates from the precipitation steps in the TTA procedure for plutonium. Because of the excessive amount of eluant necessary to separate the fission products and the resulting time required to run a separation, a method was developed to remove the Sr-Y, Ce and Pr by chemical means and Cs from the raffinate of this extraction by ion exchange. It should be noted that Cs is easily separated from Pu in the separations plant, and that is presence as a contaminate in the outer areas is not as probable as the other long-lived fission products. This fact has been born out in three years of analyzing contaminated samples from the 200 Area by the H.I. Development Divisions.

This report provides a summary of the results of a process study, requested by the Atomic Energy Commission an the recovery of krypton and xenon from irradiated uranium at the Hanford Purex Plant. This request was prompted by original Commission forecasts of the expanded requirements for Krypton-85 for commercial phosphorescent signal lights and markers and for xenon isotopes of low neutron cross-section for use in liquid xenon scintillation counters, in connection with D.M.A., government and university-sponsored work. It was requested that both Hanford and Savannah River submit order of magnitude cost estimates for recovery facilities at the respective sites for three separate design cases. The cost information developed, along with market survey information obtained-through the A. D. Little Company and Department of Defense market surveys, would serve as the basis for scheduling of the Hanford and Savannah River participation in the Commission`s overall fission rare gas recovery program.

The objective of this test is to demonstrate the feasibility of projection fuel elements for use In existing process tubing and to determine the reduction in rupture rates or hot-spot incidence so achieved. This test is to authorize, (a) charging 20 columns of bumper type fuel elements and 20 columns of control elements per reactor into B, D, DR, F, and R Reactors for irradiation up to 1200 MWD/T exposure, and (b) irradiation of four columns each of enriched (0.947%) bumper and enriched (0.947%) normal type fuel elements until two ruptures are sustained in each (or until one group shows a significant improvement).

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The object of this production test is to authorize the irradiation of samples of natural uranium for use in the fission product volatilization program. Any empty central zone PCCF and/or process tube at B, D, DR, or H Reactors will meet the requirements of this authorization.

This report provides details of Hanford Atomic Products Operation (HAPO) activities during 1956.

This report provides raw data reactor calculations for the time period of September 12, 1958 through July 21, 1960.

Experimentally determine the overall isothermal temperature coefficient of the SER up to the design operating temperatures.

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