This report presents details about the principles used for the arrangement of the Hanford 234-5 building in regards to the ventilation.

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The fused fluoride-Inconel reactor system was studied under irradiation with nominal 19 Mev deuterons as supplied by the Berkeley 60-inch cyclotron. Chemical, metallographic, magnetic susceptibility, electron diffraction and X-ray diffraction studies were made on the as-received materials, one control run and two irradiated runs. No changes in the fused fluoride fuel were noted. Accelerated intergranular corrosion and increased grain size were observed in the irradiated Inconel specimens. This report is based upon studies conducted for the Atomic Energy Commission under Contract AT-40-1-GEN-1064.

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Processes for preparing a suitable ThCl/sub 4/ electrolyte free of H/sub 2/O and C/sub 2/ were investigated including chlorination with C -Cl/sub 2/, sulfur chlorides, NaCl, and preparation from anhydrous solvents. The method selected consisted of reacting ThOCO/sub 3/ with HCl, adding NH/sub 4/Cl, and heating in inert atmosphere to drive off NH/sub 4/Cl. (T.R.H.)

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Green algae have been treated with radioactive KCN in an investigation of the effect of cyanide on photosynthesis. A multitude of products have been found to be formed in very short exposures (10 to 15 sec). One of these products has been identified with the product formed when the algae are given radioactive CO{sub 2} and nonradioactive KCN. The same product has been synthesized by a nonenzymatic cyanohydrin addition reaction on ribulose-1, 5-diphosphate. It has been shown to be a 2-carboxy-pentitol (probably mostly ribitol)-1, 5-diphosphate. Upon hydrolysis it gives an hydroxy acid (or mixture of isomers) closely related to hamamelonic acid. The significance of this and the other as yet unidentified products of cyanide interaction with a biological system is discussed with respect to the use of cyanide as an inhibitor.

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Recent correlations of slug rupture data have indicated that the failure rate increases markedly with specific slug power. After the fact flux traverses have shown that a large share of the ruptures have occurred in conjunction with flux peaks significantly higher than normally expected. If more complete in-core flux information were available, it is expected that a major portion of the ruptures could be shown as having been caused by abnormally high flux peaks. However, at present.there is neither means for continuously monitoring flux distribution nor an operating control system which can be used for effectively controlling the flux distribution in the longitudinal as well as the radial direction. It appears feasible to undertake a program at this time having the specific objective of controlling and lowering the maximum to average slug power in the Hanford Reactors. There is every reason to believe that a marked decrease in the rupture rate would result from such a course of action. The purpose of this document is to systematically examine the justification for longitudinal flux control, the apparent obstacles and limitations to efficient control, and a feasible course of action designed to fulfill the desired flux distribution objectives.

Highly convenient rules are given for the general term in the time-independent perturbation-theory expansion for the self-energy operator of quantum statistical mechanics. The rules are derived by starting from the usual formalism involving time-dependent Green's functions. The well-known formulas for thermodynamic quantities in terms of the self-energy operator are included for completeness.

Highly convenient rules are given for the general term in the time- independent perturbation-theory expansion for the self-energy operator of quantum statistical mechanics. The rules are derived by starting from the usual formalism involving time-independent Green's functions. The well-known formulas for thermodynamic quantities in terms of the self-energy operator are included for completeness. (auth)

The objective of this test is to operate one of the 1706-KE single pass tubes using sodium silicate rather than sodium dichromate as the corrosion inhibitor and to monitor the radioisotope concentration in the effluent. Single pass tube tests carried out under Production Test IP-484-A have demonstrated that when sodium silicate is added to process water the concentrations of significant radioisotopes in the effluent are reduced by a factor of two. At the concentrations investigated., the use of sodium silicate as an additional additive to all Hanford process water would cost in the neighborhood of two million dollars per year. If, however, sodium silicate, an excellent corrosion inhibitor for certain applications, would also serve to replace sodium dichromate, it would provide the added benefits of eliminating Cr{sup 51} and hexavalent chromium from the effluent. While still not economically attractive, the use of sodium silicate would be less unpalatable.

This report covers the development and qualifications of a brazing process capable of forming the bond between the instrument leads and the seal block. The process developed is unusal in that it permits the formation of a bond between austenitic stainless steel surfaces at the temperatures below 1350°F without a flux.

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The Analytical Mass Spectrometry Section at Oak Ridge National Laboratory has, for many years, been determining relative isotopic abundances from solid samples. Thus, useful analytical mass spectrometer experience with every pertinent element has been obtained. These include the 55 polyisotopic elements as well as products of irradiation and fission. The techniques used are summarized in this report. A separate page for each element lists preferred compound, loading of sample, manner of obtaining a stable ion beam, and solutions of special problems. (auth)

A vacuum analytical method for the determination of oxygen in organic compounds was developed. Several milligrams (usually 3 to 5 mg) of the organic to be analyzed are sealed in an evacuated quartz bomb along with 2.5 to 3.5 mg of an organic reducing agent. Next the bomb is fired at 1050-- 1055 deg C for 30 minutes or longer. At the end of the heating period the bomb temperature is rapidly lowered from 1055 deg C to <650 deg C. As a last step the gaseous products are removed from the bomb and the volumes of CO and H/sub 2/ are determined. From these values the percentage of oxygen can be calculated providing an appropriate blank is obtained. Compounds containing carbon, hydrogen, nitrogen, sulfur, iodine, and chlorine have been successfully analyzed for oxygen. Organic compounds containing fluorine cannot be analyzed for oxygen by this method, because fluorine reacts with quartz to form oxygen and silicon tetrafluoride. (auth)

Activities in a program to test and develop prototype fission-heated thermionic cells for space uses are reported. During the period, in-reactor tests were conducted on two W-clad U-bearing fuel emitters and one unclad type. Fuel emitter proof tests were also conducted which demonstrated 1000-hr operational capability of W-clad systems. Output power density and the temperature of heat rejection were found to have major effects on the weight- performance characteristics of the system. Advances in techniques related to W vapor deposition are reported. Descriptions of the fuel-emitter development, cell design and development, and testing of out-of-pile and in-pile cells are included. Operation of the clad-type test cells at design power and temperature led to selection of these cells for planned long-duration in-pile tests. (J.R.D.)

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The fundamental objective of the graphite temperature limit is to prevent excessive oxidation of the graphite moderator blocks with carbon dioxide and water vapor in the reactor atmosphere. Laboratory tests have shown that 10% uniform oxidation of graphite results in a loss in strength of approximately 50%. Production Test IP-725 was conducted at F Reactor for a period of six months at graphite temperatures approximately 50 and 100 C higher than the present graphite temperature limit of 650 C. The results from the F Reactor test suggest that an increase in the graphite temperature limit from 650 C to 700 C is technically feasible from the standpoint of oxidation of the graphite moderator with CO{sub 2}. Any significant additional increase was shown to lead to excessively high oxidation rates and is therefore not considered feasible. The objective of this test, therefore, is to extend the higher temperature investigations to B, C, and D Reactors. For the duration of this test, the graphite temperature limit will be increased from 650 C and 700 C, corresponding to an increase in the graphite stringer temperature limit from 735 C to 790 C. The test is expected to last for approximately six months but …

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