In an early continuation of the investigation of the radioactive isotopes of element number 43 (technetium) Segre and Seaborg produced by the deuteron and neutron bombardment of molybdenum the isotope Tc{sup 99}, which they observed to decay by means of an isomeric transition with a half-life of 6.6 hours to a lower isomeric state with a half-life greater than 40 years. The upper isomeric state of this isotope was observed by Segre and C. S. Wu to be produced in the fission of uranium and more recently R. P. Schumann and also D. C. Lincoln and W. H Sullivan working on the Plutonium Project of the Manhattan District have independently observed the beta-particles of half-life about 10 years due to the lower isomeric state. Later work by E. E. Motta and G. E. Boyd sets a more accurate value of 9.4 x 10{sup 5} years for this half-life. Since this isotope is formed in rather large amounts, namely, a fission yield of 6.2%, in the slow neutron induced fission of uranium it is now possible to isolate technetium in weighable amounts and in rather substantial quantities. For example, a uranium pile operating at a power level of 10{sup 5} kw …

The participation of phosphorus in biological oxidation-reduction reactions of the type found in glycolysis ADP + PO{sub 4}H{sup -} + 3-phosphoglyceraldehyde + DPN{sup +} = 3-phosphoglycerate{sup -} + 2H{sup +} + DPNH + ATP has suggested theories in which similar reactions are proposed for photosynthesis. In these theories the reducing power of photosynthesis is utilized not only for reduction of carbon dioxide but also, by means of coupled oxidations, for the generation of high-energy phosphate bonds, or in the last reference directly for the generation of high-energy phosphate. Since in these theories acyl phosphate is formed from inorganic phosphate, they are amenable to proof without isolation of particular intermediates, by means of radioactive phosphorus. It would be expected that the rate of conversion of inorganic phosphate to organic phosphate would be greater in light than in the dark. They have investigated this possibility under a variety of conditions and are unable to substantiate the theories.

Magnetic susceptibilities per gram atomic weight of elements 92 to 95 in most of their oxidation states were measured on 0.1 ml of solution which was 0.007 to 0.09 M in heavy element. The values obtained (all paramagnetic) in c.g.s. units x 10{sup 6} were: U(IV), 3690; Np(VI), 2060; Np(V), 4120; Np(IV), 4000; Pu(IV), 1610; Pu(III), 370; Am(III), 720. The results could be interpreted only on the basis of electronic configurations 5f{sup n}, even though susceptibilities were generally lower than the theoretical values and lower than experimental values for corresponding lanthanide cations. The lower values should be expected as a result of the Stark effect produced by fields of anions and of water dipoles. Failure of the Russell-Saunders approximation to the coupling between electrons may account for some of the error in the theoretical calculations. Wider multiplet splitting in the actinides accounts for the fact that the susceptibilities of Pu(III) and Am(III) are many-fold lower than those of Sm(III) and Eu (III) respectively.

The decay scheme of a 4.2 second neutron emitter has been investigated in detail. Chemical and physical evidence shows that it is N{sup 17}, which emits beta rays to a broad excited state of O{sup 17}, which then breaks up into a neutron plus O{sup 16}. The energy spectrum of the neutrons is determined by measuring the energies of the O{sup 16} recoils in a proportional counter. The neutrons have a most probable energy of 0.9 Mev, a 'half width' of less than .5 Mev, and an upper limit of about 2 Mev. {beta}-recoil coincidences are observed, as predicted by the Bohr-Wheeler theory, and the {beta}-ray energy is measured by absorption. The beta rays in coincidence with neutrons have an upper limit of 3.7 {+-} 0.2 Mev. Beta-rays directly to the ground stat of O{sup 17} are not observed because of high background effects, but should have an energy of 8.7 Mev. Some evidence is presented to show that energy is conserved in the {beta}-n transition through the broad excited state in O{sup 17}.

All errors due to diffraction effects in a neutron attenuation experiment are computed. Also a special experiment to measure the forward intensity of diffracted neutrons from lead and copper is described, and the results given. These agree with the theoretical values.

This document provides plots of expected rates of heat evolution rates of heat evolution from irradiated metal which may be useful in estimating the cooling water flow required in the the 212 buildings. A comparison of three sources of data found in the Project Handbook is provided. The CN 526 calculations agree very well with the estimates of 16, 32 and 64 days decay periods. CN 526 information was used for calculating the heat evolution rates shown in the following figures, since the data does not cover decay periods under 16 days, and does not include the 93{sup 239} contribution. The expected BTU/Min.(Ton) heat liberation rate vs. cooling time in days for through operating periods is shown. The operating level is taken as 2000 KW/Ton; the BTU/Min.(Ton) liberated may be scaled to higher or lower operating levels by arithmetic ratio. A similar curve in which the cooling water required (GPM/Ton) is substituted for BTU/Min.(Ton) is provided. The metric ton and a water temperature rise of 25{degree}C (45{degree}F) are assumed. The product content of the metal has been substituted for operating level in another plot. The rate of heat evolution is plotted against decay period for various operating times. A base …

This report compares the activity and disintegration energy of fission products from metal under two conditions of exposure: 200 Megawatt-days integrated exposure over a period of 180 days, and 400 Megawatt-days integrated exposure over a period of 360 days. (JL)

This is a letter of transmittal which describes the waste disposal problem at the Hanford Site. These disposal problems were discussed with the United States Geologic Survey, Atomic Energy Commission, and General Electric on October 27, 1949. Conclusions from this meeting is the main text of this letter.

The test unit is to simulate the conditions existing in the ``active``section of a pile process tube. This section is loaded with 64 slugs each of length equal to 4.3767 inches, giving an overall active length of 23.34 feet. The figure of 4.3767 inches is the overall length of the aluminum can, rather than that of the slug proper. The calculations tabulated on the accompanying data sheet are representative of the conditions of operation of the ``maximum performance tube`` in the pile. The resistance of a heater element with the specified wall thickness is such as to give a total heating of 552 Kw (corresponding to an 800 mw operating level) with a current of 13,000 amperes flowing through the tube. The heating distribution is a sine curve with a maximum heating of 33.56 Kw/ft. at the center. No attempt will be made to simulate the heating distribution in the aluminum end cap.

None

Two events of broad significance occurred in the 100B Area during this report period. These are the discovery of pimpled slugs in high concentration tubes discharged on 10-30-45 and the discovery of leaking VSR thimbles on 11-15-45. Although more extensive reports of these occurrences will be made elsewhere, these events have aspects of significance to physics and basic data will be given in this report for record purposes.

This report presents a brief discussion of a reactor incident at the 105-D area.

Data acquired from the sampling of Columbia River water January 11, 1944, is presented. The water was analyzed for temperature, dissolved oxygen, and iron. The results were compared with results from samples attained from selected taps in the C.M.X. building.

On June 1, 1948, a fire in the neoprene seal at 100-F Area potentially exposed nine to radioactive. An overnight collection of urine was made from these men and the samples submitted, along with a piece of neoprene seal, to the H.I. Development Laboratory for analysis. It is the purpose of this report to present the results of our investigation as to the type of contamination from the burning neoprene and the amount of contamination found in the urine sample.

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Since plutonium is manufactured at the Hanford Works in the 1940s, a study of its effect on biological materials is important. To determine the amount of plutonium deposited in a biological sample, it is necessary to have and accurate method for extracting plutonium from these samples. Some of the different methods for plutonium assay are reviewed and given in this paper dated November 16, 1948.

None

The D Pile was down five times for scheduled shutdowns. The fifth shutdown was of short duration for the purpose of discharging temporary ``P`` columns. Details of the shutdowns are given. Three new bismuth columns were established, Special Requests were charged into seven tubes and three Special Requests were discharged. Three tubes were charged with four-inch slugs. The power level of the F Pile has been corrected for the discrepancy noted last month. Material for irradiation under the Special Request program was charged into six tubes and the B experimental hole during the month. The effect of poison columns and rods on the temperature distribution of the pile was checked for the overall content of the pile. The F Pile gained two in hours in cold, clean reactivity during the month if allowance is made for xenon poison values corresponding to 190 MW for the beginning of the month and 200 MW at the end of the month. The graphite stringer removed from the ``D`` test hole of the D Pile on 3-12-46 was studied physical radiation effects.

This report details technical activities of the Hanford Engineer Works for the week of October 27, 1944 through November 2, 1944.

This report provides information on reactivity, temperature coefficients and energy storage to the Reactor Safeguard Committee with regard to contemplated increases in power levels.

Work of the pile physics and experimental physics groups is reported. Theoretical work is also reported.

A table summarizes all the information on blistered slugs from March 1946 to Oct. 12, 1946, as recorded in weekly technical progress letters.

The meetings divided into two parts, with reviews of work being done in radiobiology at the University of California by various members of their staff as part one, and, as part two, a meeting conducted by Dr. Shields Warren for Laboratory Directors and their representatives. For the most part papers which were reviewed were summarized material which has appeared in the literature and gave progress to date. Since the purpose of the meeting itself was more for the informal directors meetings, results of the latter are here abstracted.

On August 21, 1948, several smear samples of contamination from the inner rod room at 100-F Area were submitted for beta identification. This contamination was spread as a result of maintenance work on the horizontal rods. Urine sample were deemed advisable for two men who had been exposed while working on the rods. These urine samples were also submitted for beta analyses. The analyses of the smears showed the contamination to consist of primarily S{sup 35} (65%) and Fe{sup 59} (30%)and minor amounts of Ca (5%) and C{sup 14} (3%). No significant amount of radio iron or sulfur was found in either the feces or urine samples.