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.

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 …

The magnitude of the deviations from roundness of molded detonator heads, caused by the geometry of the part and by different materials, was investigated to provide a scientific basis which can be used to predict dimensions and tolerances of size and roundness for new heads. Injection presses were used to mold detonator heads to precision tolerances. Twenty parts were molded under optimum conditions in two different molds using both DAP filled with long glass fibers and DAP filled with asbestos. Each of the parts was analyzed for size and roundness, and the data were analyzed statistically. The results indicate: 1. Geometry is highly significant. 2. Material is highly significant. 3. Geometry and material do not interact. 4. Geometry affects magnitude of deviation from roundness. 5. Geometry affects magnitude of shrinkage.

Start of the development of new processes to extract mint can be a gradual program. The most promising of early results lies in the area of Isotopic Purification. Steps have been initiated to start development work on separation and purification of mint gas by chromatography. This method has the added advantage over columns as three gases, hydrogen, deuterium and mint may be separated in one operation. Should it appear that this method may fail, a second approach would be development of a packed column. Even with a change of the basic extraction process, isotopic purification is required and the improvement of such facilities would serve to provide the product at a reduced initial capital cost as well as reduced extraction cost. Work can proceed at the same time with development of a dissolution process. As noted in Appendix I, a unit extraction savings in the order of 20 percent can be expected since, in the most simple form, expensive furnace pots would be replaced by inexpensive crucibles.

Declassified 30 Aug 1973. An initial analysis of experimental heatup data was compiled to determine the success of module experiments designed to triple the voltage power ratio of standard TEM-9 modules. Accomplishment of this design improvement is extremely significant in the development of tabular module systems having lower power applications. With the increased voltage to power ratio, power conditioning devices will not be required to step up the module output voltage to a more usable level. Heatup data from TEM9AE S/N-1, employing 0.030-inch lead telluride washers and 0.0015-inch mica insulators, correlate very closely with performance calculations. A study was initiated to determine an optimum design for a module to be internally fueled using cobalt60. In addition, alterations to the calculation model TEMOD were made to handle the effects of gamma heating within the lead telluride washers. An experimental test program was defined which would verify the validity of the mathematical model. Additional analytical work was accomplished to correlate predicted axial heat transport rates of heat pipes with experimental data. A study of sodium heat pipe performance data revealed that a sonic vapor velocity can occur in the region between evaporator and condensor sections of the heat pipe to produce a …

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Carbon copy of a report by B. W. Hargis to Charles Batchelor. Hargis states that he agreed to interview with Alvin V. Oser, Executive Assistant District Attorney of New Orleans, Louisiana.

The objective of the test described in this report is to authorize loading KE Reactor tubes 4396, 4397, 4398, 4496, 4497, 4498, 4596, 4597, and 4598 with 0.947 enriched fuel in support of the X-2 level Battelle Northwest neutron spectrometer, when the spectrometer will be in use.

C Reactor experienced two severe fuel failures, one in process tube 2562 on 10-27-67, and one in process tube 3361 on 12-27-67, both resulting in major efforts to effect their removal. The intent of this document is to present a summary of the action taken for the removal of the failed elements.

This report is about the effort carried on through diplomatic channels and only fragmentary information us available on some attempts to get talks under way.

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This report is about derivation, usage, effects of Marihuana.

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