Failure of a vertical safety rod thimble at 105-B has led to consideration of a stainless steel (SS) thimble as replacement. 1/16 in. SS would result in 4% loss in control power of that safety rod. If all thimbles were replaced by 1/16 in. SS, there would be a reactivity loss of 790 ih.

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The synthesis of sucrose from C{sup 14}0{sub 22} by green algae has been investigated and the intermediates separated by the method of paper chromatography. It is shown that sucrose is the first free sugar appearing during photosynthesis. It is apparently formed by condensation of the glucose-I-phosphate and a fructose phosphate. A series of radioautographs of paper chromatograms of extracts from plants which have photosynthesized for different periods of time has been prepared. The results indicate that 2-phosphoglyceric acid is the first product synthesized from C0{sub 2} during photosynthesis.

This report, compiled by Mr. W. R. Lewis of the Pile Technology Division, is a revision of Document HW-15516 (January 5, 1950) in consideration of new knowledge obtained during the past year. The document discusses the technical factors involved in attaining higher power levels in the various Hanford Piles. The purpose of this presentation is to summarize the present operating limitations and the possibilities of increased production rates. The limitations discussed are: A. Reactivity and flattening; B. Aluminum thimbles; C. Graphite temperature considerations; D. Boiling or vapor binding considerations; E. Tube and slug jacket corrosion; F. Effluent water activity; G. Distortion of the biological shields; H. Radiation considerations; and I. Pile control system capacity.

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Results on the investigation of the rate of diffusion of hydrogen through several types of stainless steel and other materials of construction are reported with particular emphasis on Type 347 stainless steel.

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This manual contains the Radiation Control Standards'' and Radiation Control Procedures'' at Hanford Operations which have been established to provide the necessary control radiation exposures within Irradiation Processing Department. Provision is also made for including, in the form of Bulletins'', other radiological information of general interest to IPD personnel. The purpose of the standards is to establish firm radiological limits within which the Irradiation Processing Department will operate, and to outline our radiation control program in sufficient detail to insure uniform and consistent application throughout all IPD facilities. Radiation Control Procedures are intended to prescribe the best method of accomplishing an objective within the limitations of the Radiation Control Standards. A procedure may be changed at any time provided the suggested changes is generally agreeable to management involved, and is consistent with department policies and the Radiation Control Standards.

The feasibility of improving swelling resistance in metallic uranium by increasing the dislocation density is under investigation. Increasing the density of dislocations is expected to increase the number of sites at which fission product gas atoms are "pinned," increase the number of gas bubble nuclei, and increase mechanical strength. Dislocations are introduced by a treatment which involves deformation of metastable beta or gamma phase in uranium-rich alloys, followed by transformation. Activity has been concerned primarily with selection of uraniurnbase alloys for initial evaluation, procurement of materials, installation of specialized equipment, and development of techniques. A number of small ingots were produced, and screening tests were carried out on several analyses. These preliminary experiments were designed to show the deformation characteristics of the alloys in the metastable state as a function of rolling temperature and time. Initial results on gamma-stabilized binary alloys containing 2, 3.5, 5, and 7 wt. % Mo showed that large reductions are possible in 5 and 7 wt. % Mo alloys at450 deg C. The more dilute alloys are relatively difficult to roll, although small reductions were achieved. Aging experiments on deformed and undeformed 5 wt. % Mo alloys indicate that deformation accelerates the aging process and …

The net multiplication effect of beryllium oxide, which is due to the (n,2n) reaction, was calculated using an essentially exact calculation of the neutron spectrum as a function of energy. The upper limit of the (n,2n) cross section curve gives the unpoisoned value epsilon /sup +/ = 1.047 and the lower limit gives epsilon /sup -/ = 1,027. The behavior of the Li/sup 6/poisoned fast multiplication effect as a function of the number of collisions was studied for both beryllium and beryllium oxide. (auth)

Data on analog magnetic tape charactcristics are presented along with results from conventional and modulator playback system operational tests. Theoretical considerations imply that the modulator head should be loss sensitive to short term variations in record and playback tape speed. It is also pointed out that although a tape recorder operating at 7.5 in./sec has only 12 kcs bandwidth for sinusoidal wave forms. the record and play-back amplifiers for pulse recording can operate with other bandwidths. These amplifiers must be capable of passing a square wave with a frequency of 1.5 kcs. A square wave of such frequency represents the condition of 350 microsecond pulses with a 700 microsecond period. (J.R.D)

A study was made to determine the structural and functional adequacy of the EGCR graphite core design. Maximum stress and distortion of the core and the probable operating time before graphite cracking were determined. The major cause of stress is non-uniform fast-neutron flux, which causes non-uniform shrinkage of graphite components. The critical stress was found to be tensile. The criterion for determining the time of cracking of graphite columns appears to be the point at which the creep strain results in rupture. Column life before cracking may also be related to the maximum allowable stress at rupture. It was concluded that non-uniform shrinkage is the major cause of distortion of graphite components of the core. In general the amount by which a column tends to bow during 20-year core life exceeds the available free space. The combined internally generated and bowing stresses result in an average period before cracking of all core columns of 14 years, with a minimum period of 6 years. (M.C.G.)

A technical and economic evaluation of a mercury-cooled fast breeder reactor is presented. The objectives of the program were to establish the technical feasibility of a fast breeder reactor cooled with boiling mercury and to evaluate the long-range potential of such a reactor power plant for production of economic power. Details of the conceptual design of a 100-Mw(e) reactor and system are discussed. The power cost from a mercury cooled fast breeder reactor was estimated as 21.4 mills/kwh which is competitive with the power cost for the initial Enrico Fermi plant. It was concluded that this reactor concept is technically feasible and has promising long-range economic potential. (M.C.G.)

This document details activities of the irradiation processing department during the month of November, 1960. A general summary is included at the start of the report, after which the report is divided into the following sections: Research and Engineering Operation; Production and Reactor Operations; Facilities Engineering Operation; Employee Relations Operation; Financial Operation; and NPR Project.

A philosophy for designing wideband multistage transistor amplifiers is presented. The amplifier was visualized as an integral unit, the interstage networks constituting the elements of the amplifier unit. By designing the amplifier as a unit and adjusting the over-all response (gain and bandwidth) with the interstage time constants, an increase in gain-bandwidth product was realized over the iteratively designed amplifiers. The resulting increase in gainbandwidth product resulted from absence of the bandwidth shrinkage factor for multistage amplifiers. Formulas were derived for both a two- and three- transistor integrally designed wideband amplifier, in which shunt peaking networks were used for coupling. Experimental amplifiers were con structcd following these formulas, and the observed performance agreed quite well with the calculations. (auth)

Based on process development work at ORNL, a facility was designed for demonstration of the pot calcination process with a variety of high-level radioactive wastes. In this facility, operational and control problems associated with an integrated process can be identified and solved, procedures to improve characteristics of the calcine can be studied, and important aspects of calcine temperature distribution and fission product behavior can be observed. Installation of the facility is planned for the Hanford Atomic Products Operation. The facility can be installed in any cell or cells having certain basic features. (auth)

This is the monthly report for the Hanford Laboratories Operation, November 1962. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.

This document details activities of the Irradiation Processing Department during the month of November, 1962. A general summary is included at the start of the report, after which the report is divided into the following sections: Research and Engineering Operations; Production and Reactor Operations; Facilities Engineering Operation; Employee Relations Operation; and Financial Operation.

As TORY II-C is presently designed, a nuclear excursion would occur if the core were flooded with water. This is true even if all of the existing control rods were fully inserted. Indeed ANGIE calculations indicate that the reactor would be about 30% super-critical in such a case. There are several methods by which the core may be forced sub- critical under these extreme conditions. We will here consider only the method of introducing, directly into the core, a material which strongly absorbs neutrons. It must be possible to remove this excess `poison` prior to, or during the boost phase. Since the computer codes can be trusted to only approximately 3%, we will, for safety, insist on 40% negative reactivity to be introduced by the excess poison.