A study on low flow in tubes indicates that the below normal coolant flow is due to an abnormality in the rear hardware. It is suggested that reaming the rear Parker fittings on the tubes and subsequently inspecting the venturi gauges is an good solution.

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This document describes the detailed test procedures to be used during the initial phases of the physics test program--the approach to critical and minimum critical size tests. During these initial phases, several physics characteristics of the reactor will be evaluated in addition to determination of the critical loading. Overall flux distributions will be determined in the critical pile and used to evaluate the lattice buckling characteristics. Theoretical calculations normalized to experimental values from exponential and PCTR tests have been used for estimating the experimental results for each phase. The startup tests will be used to verify the preliminary calculations and to define the reactor characteristics within the precision required for safe and efficient operation of the reactor. Detailed and accepted test procedures are required for maximum test efficiency and reactor safety during the physics test program and for sufficient overall scheduling into the N-Reactor operational test program. Hazards` analyses have been performed and are presented for cases which are unique to the physics startup tests or significantly differ from the Design Hazards Review.

Carbon-14 is by far the most popular of the labeled isotopes because of its adaptability to so many chemical compounds and its relatively harmless characteristic beta radiation. Because the inert gas atmosphere contains up to 30% nitrogen, carbon-14 is generated within the K Reactors by the conversion of nitrogen-14, and if not immediately oxidized, carbon-14 may remain in the reactor core for some time. It is eventually oxidized and escapes when the outward gas leakage from the reactor is vented to the stack. Production Test 124 was authorized to determine if carbon-14 could be extracted from the K gas as a profitable by-product. It was concluded that as much as 500--600 curies per year of carbon-14 could be recovered if both K Reactors were provided with relatively simple extraction facilities. This is about twice the amount of this product for which there is a current market at the present price level of approximately $3,000/curie. The grade (as specific activity) of the product recovered in the production test was low -- ranging from 3 to 26 millicuries per mol. Substantial upgrading (perhaps by a factor of 10X to 100X) is possible by skimming techniques and reduced oxidation of normal carbon at …

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Future operation of B-Plant for Phase I fission product processing involves may of the hazards associated with current chemical Processing Department activities in both the Purex and Redox Plants. The specific B-Plant hazards under Phase I operations are discussed in this report from the standpoint of comparable Purex and Redox hazards.

Temperature calculations were made on a proposed design of an uncooled horizonal control rod (HCR) for the K Reactors. The calculations were performed with the aid of a FORTRAN coded heat transfer program for the UNIVAC 1107. The results of the calculations indicate that such a control rod is feasible for.4400 Mw and 5000 Mw operation provided certain precautions are taken. These precautions include assuring good contact between the rod and the graphite in the high flux regions and Providing reasonable contact between the graphite stack and the graphite slider plates that will be placed in the bottom of the rod channels prior to rod insertion and use.

On January 22, 1960, HW-63487 Piping Changes for Increased Production at B, D, DR, F, C, and R Reactors, was published. This study investigates the valve pit piping, front and rear face piping,and effluent lines between the 105 Buildings,and the retention basins to determine modifications necessary to increase power levels in the 100-B, D, DR, F, C, and H Areas by increasing either or both temperatures and flows. The study was based on detailed hydraulic and stress calculations of the existing and proposed piping systems which because of their detailed and voluminous nature were not included in the study. It is the purpose of this study to document, in so far as possible, these calculations together with pertinent information which was not included in the original study.

Hanford production reactor operation requires the rejection of very large heat loads. At the present time the heat load is rejected to the Columbia River by the reactor effluent. At low river flows the hot effluent can have appreciable effects on river temperatures. The purpose of this study is to evaluate the feasibility and costs of Cooling Towers as a means of reducing the heat load rejected to the Columbia River. After evaluation of published information, available data, and Hanford plant conditions, it is concluded that: (1) That an induced draft cooling tower, because of its longer cooling range,, would be an effective cooling device for reduction of gross heat load rejected to the Columbia River. Additional study will be required to determine effective use on an area to area basis. (2) That a basically wood, counter-flow, induced draft cooling tower could be installed for approximately $1600 to $2000 per megawatt capacity. This cost is a probable minimum and might be increased by the cost of auxiliary features required for radiation control. (3) That additional study and developmental testing would be required to determine the extent of contamination problems which would result from the cooling tower installation. These problems would …

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Data transmission over telephone lines involves the acceptance of serialized binary data, modulation of the data to a signal suitable to the bandwidth of the telephone. channel, transmission of the signal over the line, reception at the receiving end and demodulation of the signal to reproduce the original binary data. One typical application of data communication is between a low-speed terminal and a computer. In such a case, full-duplex operation is often desirable (i,e., transmission of information on the line in both directions simultaneously). The data set described in this report operates full-duplex and provides for channelization of the telephone line for the simultaneous use of several data sets. The data set can either be coupled to leased telephone lines or acoustically coupled to any telephone.

The purpose of this study is to determine if a hazardous condition is created by accidental closing of the coolant loop isolation valves�while the reactor is operating.

The effective delayed neutron characteristics of a reactor are dependent on the relative fission rates in the various fissionable isotopes present. The delayed characteristics of the production reactors are presented as a function of exposure.

C Reactor was shut down on a scheduled basis at 8:30 a.m. March 6, 1961 for the purpose of overboring 17 process channels. this report will cover that outage and discuss problems encountered in completing the tasks involved in overboring.

A continued decrease in flow measured during the periodic high velocity flushes indicated that corrosion buildup in the high tank discharge lines was deceasing backup flow to the reactor. An accurate determination of the high tank flow rate to the reactor was needed to evaluate present back-up adequacy. Riser pressure and flow rate were also measured with throttled high tank discharge lines to establish the low flow and critical portion of the reactor hydraulic characteristic curve. This report presents the numerical results of the test conducted on October 4, 1962.

In 1961, large-size, smooth-bore, Zircaloy process tubes were installed in C-Reactor graphite channels that had been enlarged to 2.275 inches. These tubes were installed to provide a test and demonstration facility for the concept of overboring as a means of securing significant improvement in the production capability of the reactors, After two years of facility operation, it is now appropriate to consider the extent to which original objectives have been achieved, to re-examine the original objectives, and to consider the best future use of this unique facility. This report presents the general results of such a review and re-examination in more detail.

The objective of this test is to evaluate the effects of oil quenching, alpha annealing, and an Al-Si braze pre-canning treatment on the irradiation behavior of hot-die-sized fuel elements.

An increase in the flow of water from the lower depths of the Grand Coulee Reservoir was used to lower the river temperature at Hanford Atomic Products Operation (HAPO). A net average daily reduction of over 1 C resulted. The average for one day varied from 1.7 to 0.2 C. Before the dam control period, the Bonneville Power Administration transferred load from Grand Coulee Dam to other dams in order to conserve cold water. The authors calculate that there was more value to HAPO from this transfer than the combined effects of river bed losses and/or any variance in scheduled or base loads.

This report describes a study which was made to determine possible changes in mixer placement at H reactor because of the change from an enriched core load to a natural load and to evaluate movement of metal charges 8 inches downstream. Also studied was the effect of short charging on tube life and mixer position. Special consideration was given to the fact that H reactor will shut down in approximately seven months.

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Results of the study on the best charge length of enriched fuel to be used in the reactors Indicate that with the present quality of fuel elements there is no economic incentive to change the charge lengths from those currently being used. The expected returns for operating D and C reactors at optimum conditions with different length enriched fuel charges are given in figures. Detailed results from calculations concerning the other reactors would also exhibit similar trends.

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The authors calculate the branching ratio {Lambda}(P {yields} {ell}{sup +}{ell}{sup -})/{Lambda}(P {yields} {gamma}{gamma}) to lowest contributing order in quantum electrodynamics, with a vector meson model for the pseudoscalar meson form factor. They treat the processes {eta} {yields} {mu}{sup +}{mu}{sup -}; {eta} {yields} e{sup +}e{sup -}; K{sub 2}{sup 0} {yields} {mu}{sup +}{mu}{sup -}; K{sub 2}{sup 0} {yields} e{sup +}e{sup -}; {pi}{sup 0} {yields} e{sup +}e{sup -}. Results are compared with those of previous calculations.

A test was performed at the Shippingport PWR, whose purpose was to determine the amount of heat the fuel shipping container cooling system was capable of removing while in a state of equilibrium. Studies were also conducted to determine if after four hours of operation, the increase of the internal wall temperature was less than 30 deg F, and finally, to determine the effects of loss of cooling water from the fuel shipping container. (auth)