This report is a summary of Pros and Cons of domestic distribution of USIA materials.

This report's purpose is to present the constitutional and historical background of the "interregnum" question and to describe the precedents established on these occasions. It discusses when the date set for the inauguration of the president has fallen on a Sunday.

A study of the incorporation of {sup 14}CO{sub 2} into cell components of synchronously growing Chlorella pyrenoidosa has shown that DNA is synthesized primarily during the latter stages of the cell cycle prior to cell division. RNA was synthesized at an approximately equal rate during each of the three phases of the cell growth studied. No major differences were noted in the incorporation of {sup 14}CO{sub 2} into the soluble cell components in these long-term incorporation studies.

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The recently completed 25-inch hydrogen bubble chamber combines excellent picture quality with a fast operating cycle. The chamber has a unique optical system and is designed to take several pictures each Bevatron pulse, in conjunction with the Bevatron rapid beam ejection system. At present the chamber operates twice per Bevatron pulse. The general features of the chamber constructiosn are shown in Figs. 1 and 2. The chamber is ten inches deep at the narrowest point. The magnet is of conventional water cooled design and in present operation produces a vertical field of 18.5 kgauss. With suitable generators it has produced a field of 22.8 kgauss. The most important new features are discussed below.

Angular distribution and kinetic-energy spectra of fragments, and cross sections for fission of gold with 68- to 124-Mev C{sup 12} ions have been obtained by observation of the fragments in two types of detectors, gas scintillation chambers and silicon p-n junctions. From the parameters used to fit the angular distributions to the theoretical curves of Halpern and Strutinski, we have obtained the average excitation energy of the fissioning nucleus at the time of fission. This quantity is approximately 25 Mev, which is nearly independent of bombarding energy, suggesting that fission is preceded by the emission of several particles from the compound nucleus. The fission cross section increases from a value of 100 mb at 68 Mev to 1.28 b. at 124 Mev. Over this range of bombarding energies, the total fragment kinetic-energy release rises from 142 {+-} 6 to 146 {+-} 6 Mev. At all bombarding energies, the variation of laboratory-system kinetic energy of the fragments with laboratory-system angle indicates full momentum transfer by the bombarding particle to the fissioning system.

Agenda for improving and developing the agricultural, commercial, military, legislative and public aspects of the city of Sweetwater, Texas in the year of 1963-1964. Former WASP instructor, Paul Hill, is listed as one of the Co-Chairmen.

Abstract: A definitive investigation of the boron-carbon equilibrium system is being made by X-ray diffraction, metallographic, and thermal analytical techniques. Additional baron-carbon alloys have been prepared by sintering and arc-melting compacts prepared from boron and high-purity graphite. Metallographic examinations of these alloys are in agreement with alloys previously preapred from lampblack. X-ray investigation of sintered compacts indicates that the solubility range of boron carbide extends almost to pure boron. Boron of various purities has been annealed for times up to four hours, but no structure other than beta-rhombohedral has been detected. Very high purity boron (10 ppm impurity) has been obtained for the study of allotropy and the equilibrium relationships at very dilute carbon contents.

Abstract: "As part of a program entitled "Improved Zirconium Alloys" a brief summary of a present zirconium research at various organizations has been prepared. Information was obtained by telephone and personnel contact; and these discussions, along with the organization and personnel, are presented."

Short-time tensile tests were conducted on irradiated (2 x 10/sup 20/ nvt) and unirradiated Hastelloy-N bar from heats 5911 and 6252. No significant difference in mechanical properties was noted between the two heats. The 1200/sup 0/F ultimate tensile strength was decreased by irradiation from 65 to 80 ksi and 48 to 52 ksi. The 1400/sup 0/F ultimate tensile strength was decreased from 45 to 51 ksi to 32 to 34 ksi. The yield strength was not greatly affected by irradiation at either 1200 or 1400/sup 0/F. The 1200/sup 0/F elongation at fracture was decreased from 15 to 45% to 5 to 11%. The 1400/sup 0/F ductility was decreased from 8 to 26% to 1 to 1-1/2%. Unirradiated uniaxial stress-rupture tests were conducted at both AI and ORNL. No definite difference in stress-rupture properties between heats was noted at either 1200 or 1400/sup 0/F in ORNL tests, although some of the 1400/sup 0/F stress-rupture tests indicated that heat 6252 exhibited greater ductility. The AI verification tests showed a definite ductility difference, with heat 6252 exhibiting greater ductility. This phenomenon was attributed to an inhibition in crack propagation due to microsegregation.

This report details activities of the N-Reactor Department during the month of September 1964.

Reactor irradiation of naturally-occurring thorium-232 produces both uranium-233 and the undesirable isotopic contaminant, uranium-232. Uranium-232 decays (74 year half-life) to thorium-228, which in turn decays with a two year half-life to a string of comparatively short-lived daughters some of which emit very highly energetic beta and gamma radiations. It is generally desirable to accumulate a substantial inventory of irradiated thoria before diverting a plant such as Purex temporarily to chemical processing of the thoria. Especially during this waiting period significant amounts of thorium-228 can be formed from decay of uranium-232, thus causing isotopic contamination of the recovered thorium-232. The purpose of this report is to show how thorium-228 builds up in thoria which has been irradiated under several different conditions and then allowed to cool for a varying period of time. The results are shown in Figures 1 through 4. Derivation of the results is described in Appendix I.

This report gives the status of production test control tube loadings in reactor process tubes containing significant amounts of SS materials. The data are given in table form. For further description of column headings and the current discharge goal exposure plan refer to Document DUN-1048.

This report details activities of the N-Reactor Department during the month of May 1964.

This document details activities of the N-Reactor Department during the month of March 1963.

Failure of reactor rear face connectors is a problem at the reactors. The vibration has been studied at H and F Reactors to assist in the development of a permanent replacement for these connectors. Vibration data were otained from rear nozzles, connectors, and crossheaders within the process tube pattern for the following operating conditions: full cold water flow prior to reactor startup, normal operating power level, and during transition from shutdown to normal operating power level. The vibration patterns at 105-F and 105-H were similar in magnitude. Oscillograph data are presented.

The loss associated with low goaling rupture-prone material is quite small compared to the benefits. There is an optimum goal exposure for a given metal quality. At this optimum exposure the loss associated with irradiating rupture-prone material is minimized. Reasonable decision rules are as follows: Discharge, at the first opportunity, tubes containing rupture-prone material whose exposures are equal to or greater than 50 percent of normal goal. Discharge tubes under 50 percent of normal goal which would be expected to reach 70 percent of normal goal before the next scheduled outage. Irradiate all tubes containing rupture-prone material whose exposures will not be expected to exceed 70 percent of normal goal before the next scheduled outage. Discharge all tubes containing rupture-prone material, regardless of exposure, if an additional rupture is incurred in the lot. Return unirradiated rupture-prone material to Production Fuels Section as reject material.

The scheduled termination of PT IP-659-AC, presently being irradiated in F Reactor, will result in discharge of 105 columns of enriched uranium (0.947 w/o U-235) at less than 50 per cent of the goal exposure. The test block is currently scheduled to be replaced with natural uranium columns. Since F Reactor is on a semiblock discharge plan (alternate rows), subsequent operating plans would require that 64 of these replacement columns of natural uranium be likewise discharged during the scheduled outage in May of 1964 at less than 50 per cent of goal. It appears desirable to minimize the economic costs of the production test by an alternative discharge scheme (e.g., interim poison irradiation). The objective of this supplement is to soften the economic impact of low exposure fuel discharge scheduled by IP-659-AC and simultaneously to obtain a useful alternate product by irradiating nine columns of Li-Al and Bismuth in a ``striped`` charge.

Heat discharged to the Columbia River in reactor cooling water is one of the more important pollutants from Hanford operations. The effect of this heat on river temperatures has been studied for several years, primarily because of the potential effect on the Columbia River fisheries. This document presents a summary of recent river temperature experience, with comparison data for a better perspective.

This document summarizes the graphite treatment studies conducted under Design Test 1136 in connection with the retubing of the K Reactors with zirconium tubes.

The purpose of this test was to further evaluate the behavior of N Reactor fuel elements at conditions equivalent to or more severe than those expected at N Reactor. A. Date Charged: June 2, 1963: B. Fuel Elements: A total of fourteen 23.2 inch NAEl elements with an enrichment of 0.947 per cent were charged. C. Exposure: The fuel elements were charged a total of 5,661 hours. Of this period, the reactor operated 3,841 hours and the loop was at desired operating conditions 3, 292 hours or 86 per cent of reactor operating time. D. Date Discharged: January 24, 1964. E. Reason for Discharge: Goal exposure reached.

Because of the questionable performance of the 190-DR steam backup system during the power outage of April 6, 1962, it is felt that a general review of the DR secondary water system capabilities and the standby status of the pumping units is warranted. This report shall briefly describe the performance of the steam backup system during the April 6 power outage and the subsequent power outage of July 10, 1962. Since the former outage, tests have been conducted on the steam pump units to determine their capabilities; the test results are presented in this report. A statement of the generally accepted criteria for secondary coolant system adequacy is included and recommendations for meeting the criteria at DR reactor are presented.

This report covers the efforts of the Laboratory in an investigation of the graphite distortion in the ``C`` reactor at Hanford. The particular aspects of the problem to be covered by the Laboratory were possible ``fixes`` to the control rod sticking problem caused by VSR channel distortion.

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