There is now experimental evidence for selectivity between the amino acid and the nucleic acid base which is the beginning of the chemical translation process from one linear system to the other. The linear system of the nucleic acid is, of course, an excellent place to store the information, whereas the linear system of the polypeptide, on the other hand, is the versatile system which can perform many different types of reactions but is unable to store information reliably. The experiments the author has described here may represent the beginning of the method of coupling of those two essential qualities which are required for the generation and evolution of a living organism.

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This document provides data collected by the Controlled Temperature Tensile Capsule (TISR-243).

Design criteria are given for a conceptual reprocessing plant capable of processing HTGR-type graphite-based fuel. The single-purpose plant is designed to reprocess 260 metric tons of fuel per year consisting of HTGR reference-type and Fort St. Vrain fuel plus a small amount of Peach Bottom fuel. The design incorporates a burn-leach type headend, separate modified Acid-thorex flowsheets for solvent extraction recovery of the heavy metals from both the fertile and fissile particles, and denitration of both the U-233 and U-235; in addition, extended storage of thorium as a nitrate solution is provided, high- and intermediate-level wastes are converted to granular solids in a fluidized-bed calciner and stored indefinitely on site, and low-level waste is essentially completely decontaminated. These design criteria will be used by an Architect-Engineer to prepare a capital cost estimate for the conceptual plant. The cost estimate will be part of an HTGR Reference Plant Study to develop a reprocessing charge for those HTGR fuels that will be received by the AEC for financial settlement.

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This report presents the details of the activities of Douglas United Nuclear at the Hanford site during the month of November 1968.

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Electrons were injected from a 3.3-MeV 300-A accelerator into a circular orbit in a pulsed magnetic field. Trapped ring currents of 150 A (4 x 10{sup 12} electrons) were magnetically compressed from 19 cm to 3.5 cm radii and simultaneously accelerated from 3.3 MeV to 18 MeV in energy. The rms dimensions of the cross section of the ring after compression were a = 2.3 {+-} 0.2 mm radially and b = 1.6 {+-} 0.2 mm axially. The lifetime of the ring was typically 5.5 msec, and was determined by the decay of the magnetic field after compression. This lifetime could be decreased by the addition of hydrogen gas, indicating the focusing effect of the trapped positive ions.

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The purpose of this Conceptual Facility Design Description (CFDD) is to provide a technical description of the Inert Gas Cell Examination Facility such that agreement with RDT on a Conceptual Design can be reached . The CFDD also serves to establish a common understanding of the facility concept among all responsible FFTF Project parties including the Architect Engineer and Reactor Designer. Included are functions and design requirements, a physical description of the facility, safety considerations, principles of operation, and maintenance principles.

The FFTF Radioactive Waste System provides the equipment and facilities required for the routine collection, transfer, storage, and disposal of radioactive liquid and solid wastes. Radioactive solid wastes and radioactive liquid wastes not normally piped t o the Radioactive Waste System Receiving tanks, are packaged inappropriate containers by the systems generating the waste for collection and disposal by the Radioactive Waste System. Included are functions and design requirements, a physical description of the system, safety considerations, principles of operation, and maintenance principles.

RX-09-CB and LX-07 were made to supply material for testing. Both were made in the 300-gallon kettle in 250-pound batches which were then blended into 1,000-pound lots. An RX-09 with no plasticizer (HMX and DNPA) was made in the 30-liter reactor for special gap and friction studies. Approximately 20 pounds of DNPOH, supplied by Aerojet, was converted to DNPA and polymerized by the emulsion polymerization process. Work on high surface area PETN continued by precipitation recrystallizing two 10 kg batches; one to supply material for detonator applications to Mound Laboratory and the other to supply high surface area PETN to LRL for special applications. Surface area for this batch was 21,200 cm{sup 2}/gm. The detonator material had a surface area of 14,500 cm{sup 2}/gm. A system duplicating the English method for achieving high surface area has been completed with the installation of the 8-inch Micronizer, and two preliminary trials of one pound each have been made. Surface areas were 20,900 and 14,900 cm{sup 2}/gm. The system is being modified slightly to eliminate the problems incurred during these trial runs and preparations are in process for making a 10 kg batch to be shipped to Mound.

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This report is a summary of several studies made by the author during 1967, and early 1968, while providing technical assistance to the Advanced Concepts and Planning Section. An attempt has been made to reduce the data to a usable form which will enable the reader to estimate the production of a particular isotope and the production of weapons grade plutonium that accompanies the co-product loading for different Uranium-235 concentrations of the driver fuels. It should be emphasized that the production data shown in this document do not constitute an engineering study of the loading. As the safety analysis has not been performed and only minimal hydrokinetics have been studied, it is imperative that the use of the data contained in this report be used only for planning and estimating work. if any particular loading were to become a reality, a detailed engineering study would be required for that loading. Although the B Reactor has been deactivated it is included in the report along with the C and K Reactors. Hence, it is possible to make estimates of the capabilities of the entire Hanford single pass reactor complex. Although Oralloy fuel for the Hanford reactors for isotope production has not …

This report deals with the monthly production from the C Reactor at Hanford, and the effluent water data for 1968.

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RX-04-CW, LX-07-1, and RX-09-CD were tested. The RX-04-CW and LX-07-1 are not complete; however, results so far show the TX-04-CW comparable in sensitivity to PBX 9404 while the LX-07-1 is less sensitive at 14{degree}. The RX-09-CD was slightly more sensitive than the RX-09-CB previously tested.

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