BS>Intercalibration data for various temperature sensing elements in the reactor coolant system are obtained and compared with calculated source activity levels and observed channel levels. The readings of 20 of the 62 core thermocouples were either less than 400 deg F, which was off scale on the recorder, or were plus or minus 20 deg F from the calibrating resistance thermometer temperatures. The remainder of the readings were within plus or minus 3% of the temperatures of the calibrating thermometers which were used as a standard of comparison. The main coolant loop resistance thermometers all read within plus or minus 0.2% of the calibrating thermometers. The data from the nuclear source range instrumentation indicated a level ranging from less than 1.7 cps to 31 cps; Channel A indicating the highest. The recorded source activity levels were generally higher than the calculated source activity levels as they should be. There appeared to be no correlation between coolant temperature and source log level source range indications. (N.W.R.)

The authors report a study of the reaction K{sup -} + p {yields} {Lambda}{sup 0} + {pi}{sup +} + {pi}{sup -} produced by 1.15 Gev/c K{sup -} mesons and observed in the Lawrence Radiation Laboratory's 15-in. hydrogen bubble chamber. A preliminary report of these results was presented at the 1960 Rochester Conference. The beam was purified by two velocity spectrometers. A hyperon/observed during the run and the preliminary cross sections for various K{sup -} reactions at 1.15 Bev/c have been reported previously. Reaction (1) was the first one selected for detailed study, because it appeared to take place with relatively large probability and because the event, a 2-prong interaction accompanied by a V, was easily identified. In a volume of the chamber sufficiently restricted so that the scanning efficiency was near 100%, 255 such events were found. These events were measured, and the track data supplied to a computer which tested each event for goodness of fit to various kinematic hypotheses. The possible reactions, the distribution of events, and the corresponding cross sections are given in Table I. An event was placed in a given category of Table I if the {chi}{sup 2} probability for the other hypotheses was < …

Quarterly report describing progress on a project to develop and evaluate high-temperature tungsten alloys. This report discusses properties for specific base alloys at room temperature and under high temperatures.

From foreword: This report presents the results of a study on the stability of phosphors under high energy beta radiation.

"Abstract: An evaluation of a modulator flux sensitive playback head to be used with an analog magnetic recorder for nuclear pulse information storage was made. The modulator head was found unsultable. A pulse stretching unit was constructed which takes pulses from a standard linear pulse amplifier and provides an output signal suitable for driving a recording head."

Irradiation of a third thermocouple train with a thermocouple element of the same design as used on the previous two trains, but with different heater elements, is authorized to an exposure no greater than 1000 MWD/T. A second decontamination of KER-1 using the same procedures as for the first decontamination is also authorized.

This study was developed to provide a correlation for the evaluation of the pile C{sub RI}/Tube C{sub RI} ratio (alpha value) for each of the Hanford reactors.

The scope design for Birch recovery at Redox was presented in September 12, 1960. Final plutonium purification and decontamination by anion exchange in a pulsed-bed contactor under development by Hanford Laboratories was proposed. Potential advantages of low cost and improved operability were anticipated from the new contactor; when these were not demonstrated in the development work in time to meet project schedules, it was decided to revert to the Higgins-type contactor for which considerable Purex operating experience can be drawn upon for design bases. This scope revision presents the necessary changes to cover the change of contactors.

Information concerning the pressure-flow relations in reactor process tubes at very low heat generation rates is of value for determining flow requirements during shutdown conditions. Since such information is quite difficult to calculate when boiling occurs, a brief laboratory investigation was conducted to obtain experimental data. The data obtained for BDF geometry are recorded in this report for distribution to those persons having an interest in the application of the results to reactor operation.

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Questions relating to the payment of the State matching contribution to the Teacher Retirement System occurring during the fiscal year ending August 31st, 1959.

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: May an insurer who has made a deposit with the State Treasurer under Article 3.15 of the Code elect to have its deposit considered as held under Article 1.10, paragraph 17 of the Code.

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Is the General Land Office authorized under Article 8225, V.A.C.S., to sell State owned land to the San Patricio County Navigation District No. 1 when said land is located outside the boundaries of such district?

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Questions concerning the legal determination of restoration of recipients of public assistance, who have been judicially declared to be of unsound mind or mentally incompetent, under provisions of the Texas Mental Health Code.

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Office of County Clerk and District Clerk becoming separated in view of increase in population over 8,000 inhabitants according to the 1960 Federal Census.

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.

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.

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.

Abstract: A method is given for the rapid and accurate numerical integration of integrals of the form [integral] [superscript infinity] [subscript infinity] f(x) [golden ratio constant] (x) dx, where f(x) is "smooth."

When the construction of the confinement facilities for Hanford production reactors is completed, the potential for contaminating the environment with accidentally released fission products will be greatly reduced. This was demonstrated already when rupture debris burned in the rear face area of one of the reactors in which the fog spray was installed and ready for service. The fog spray effectively prevented the spread of contamination to the ventilation equipment downstream of the rear face enclosure. Also, the commercially- available absolute filters and charcoal beds will significantly decontaminate the exhaust air, stream of all fission products except the noble gases. Laboratory studies indicate that the filter system should remove at least 50 percent of all fission product halogen vapors and over 90 percent of the particulate matter released from a nuclear incident. In addition, the charcoal beds should provide an additional 90 to 95 percent decontamination of the halogens that manage to pass through the filter. It is not expected that any of the noble gases released will be removed by this system. Laboratory studies, in general, substantiate previous estimates on the release of fission products from overheated uranium fuels. The theoretical estimates are quite accurate for the volatile and …

Tests were conducted to compare the specific isotopic fission product activities with those of delayed neutron emitters which are monitored by the FEDAL System, and to obtain irformation on the source of activity observed in the PWR coolant. The monitors detected definite activity bursts of delayed neutrons during load increases, which indicated a rupture of the core blanket element. A radiochemical analysis of the coolant data did not show any unusual activity bursts, thus indicating a fuel element failure. It was concluded that the discrepancy in measurements is caused by methods not specifying exactly the time for taking radiochemical samples. The data are tabulated as activity and power output, and given as a function of time. A comparison is given of the activities in the primary coolant for April, June, and July of 1958. (B.O.G.)

None

A feed preparation and solvent extraction flowsheet was developed for the recovery and decontamination of highly enriched uranium from the LAPRE-II reactor fuel solution. The fuel solution, U(IV) in concentrated H/sub 3/PO/sup 4/ ' was dilutad, Fe(NO/sub 3/)/sub 3/ added to complex phosphate and supply salting strength, NaNO/sub 2/ added to oxidize U(IV) to U(VI) so that U may be extracted efficiently with 6% TBP. The flowsheet is designed for operation in noncritically safe equipment. (auth)

A preliminary report on the operations and procedures for handling a 125- w thermoelectric generator and its isotopic heat source is presented. Full-scale mock-ups were used to develop the procedures. A cylindrical metal block of Inconel X will be remotely loaded with an isotope at ORNL. The block will then be sealed snd loaded into a specially designed cask and shipped by rail to the Martin nuclear hot cell facility, where the second phase of the operation will be conducted. (W.D.M.)

Core dimensions and nuclear parameters were calculated for a sodium- cooled fast reactor containing UC fuel elements in a skewed hexagonal array. (C.J.G.)