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Preliminary designs and costs have been developed for nuclear fuel head-end reprocessing facilities integral with a large High-Temperature Gas-Cooled Reactor (HTGR) power plant.

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The second-order nonlinear differential equation for the rotation of Mercury is shown to imply locked-in motion when the period is within the range (2T/3) [1-{lambda} cos 2{pi}t/T {+-} 2/3 (21{lambda}e/2){sup 1/2}], where e is the eccentricity and T the period of Mercury's orbit, the time t is measured from perihelion, and {lambda} = (B-A)/C measures the planet's distortion. For values near 2T/3, the instantaneous period oscillates about 2T/3 with period (21{lambda}e/2){sup -1/2}T.

Thermal diffusivity of Al-clad MTR-ETR type fuel plates was measured from room temperature to 600/sup 0/C. (DLC)

Plant nutrition was studied as a relation between aerobic respiration and ion uptake in barley. Potassium, chlorine, lithium, sodium, calcium, sulfates, and bicarbonates were studied by root absorption in varying concentrations of carbon dioxide atmospheres. (PSB)

This report for June 1966, from the Chemical Processing Department at HAPO, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance: Financial operations; facilities engineering; research; and employee relations.

This report to the FEDC Working Committee details activities in N-Reactor fuel element fabrication and materials testing for the time period of September 1965 to January 1966.

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.

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The meetings were held on December 6 and 7, 1965 in the 325 Building conference room at PNL. The objectives of the meetings were: (1) To review the status of the ceramic coproduct target element fabrication technology and the subsequent extraction processing technology of irradiated elements as developed at PNL. (2) To discuss the feasibility of performing extraction studies of irradiated coproduct target elements at the SRL pilot plant facilities in demonstrating the capability of coproduct production in N-Reactor. (3) To identify potential problem areas that could arise when the laboratory scale extraction process would be performed on a pilot plant scale in the existing SRL facility.

The technical basis and criteria for five requirements are presented. Requirement 1 is that the coproduct target element shall be compatible with the driver element in the environment of the N-Reactor primary loop. Requirement 2 is that the target element shall be compatible with nuclear safety requirements under all credible accident conditions. Requirement 3 is that the coproduct element shall be unmistakable from other fuel element models in use or expected to be in use during the period 1966-68. Requirement 4 is that the target element shall have a degree of reliability that is compatible with reactor performance objectives. Requirement 5 is that the target element shall be compatible with procedures for post-irradiation processing.

This report analyses the crude oils from many oilfields within the U.S.

The ''handbook'' density for LiAlO/sub 2/ is 2.55 g/cc. Recent data show that it should be revised to 2.62 g/cc. In the future densities reported as percent of theoretical should be based on 2.62 g/cc as being 100 percent. Values quoted on this basis will be more realistic. In order to avoid confusion it will be necessary to state which number percent of theoretical density are based upon--that is, ''2.62 g/cc = 100 percent,'' or ''2.55 g/cc = 100 percent.'' For the convenience of those working directly with the material, a conversion chart is included along with a table which gives density (g/cc) versus percent density based on 2.62 g/cc.

In recent years there has been an increased interest in the use of transuranium isctopes for special power applications. Moreover, as the civilian power reactor economy expands, a large quantity of such isotopes will be formed in reactors using slightly enriched uranium fuel and, more particularly, in reactors which recycle the higher isotopes they form. This report, consisting mainly of computer printouts, indicates the yields of transuranium isotopes from different fueling methods. Since water reactors will be the predominate type of power reactor for at least a decade, most of the values presented here are derived from simulated water reactors.