The Magnetic Mirror Fusion Program is one of the two main-line fusion efforts in the United States. Starting from the simple axisymmetric mirror concept in the 1950's, the program has successfully overcome gross flute-type instabilities (using minimum-B magnetic fields), and the most serious of the micro-instabilities which plagued it (the drift-cyclotron loss-cone mode). Dense plasmas approaching the temperature range of interest for fusion have been created (n/sub p/ = 10/sup 14//cc at 10 to 12 keV). At the same time, rather extensive conceptual design studies of possible mirror configurations have led to three principle designs of interest: the standard mirror fission-fusion hybrid, tandem mirror, and the field-reversed mirror. The lectures will discuss these three concepts in turn. There will be no discussion of diagnostics for the mirror machine in these lectures, but typical plasma parameters will be given for each type of machine, and the diagnostic requirements will be apparent. In a working fusion reactor, diagnostics will be required for operational control, and remarks will be made on this subject.

Microstructural analysis of sessile drop experiments of silicon on mullite indicate reaction at the liquid solid interface which is especially severe after ten hours. Compositional variation including higher purity and elimination of the glass phase did not affect the reaction. The increased surface area of porous samples caused severe structural damage to these substrates. Reaction phases are found away from the interface after long exposure. Compositional variations have been found to lower the thermal expansion of the mullite to the expansion of silicon. The addition of silica to a standard mullite body is found to increase the amount of glass phase while lowering expansion. It has also been found that a mixture of fused mullite and fused silica fires to a body with thermal expansion very near that of silicon. The thermal expansion of silicon was measured in the 111 crystal direction and found to concur with published data.

This report looks at the background of Trade Adjustment Assistance (TAA) in the Trade Expansion Act of 1962, which was created by Congress. It then discusses how the 112th Congress is considering legislative action to extend the TAA - including two issues: how necessary or appropriate the extension is, and whether or not three proposed bills should be voted upon separately.

This report discusses section 123 of the Atomic Energy Act (AEA), the specific requirements of which must be met in order for the United States to engage in civilian nuclear cooperation with other states. The AEA also provides for exemptions to these requirements, export control licensing procedures, and criteria for terminating cooperation.

This report presents research objectives, discusses activities, and presents technical progress for the period April 1, 1993 through June 31, 1993 on Contract No. DE-FC21-86LC11084 with the Department of Energy, Laramie Project Office. The scope of the research program and the continuation is to study interacting hydrologic, geotechnical, and chemical factors affecting the behavior and disposal of combusted processed oil shale. The research combines bench-scale testing with large scale research sufficient to describe commercial scale embankment behavior. The large scale approach was accomplished by establishing five lysimeters, each 7.3 {times} 3.0 {times} 3.0 m deep, filled with processed oil shale that has been retorted and combusted by the Lurgi-Ruhrgas (Lurgi) process. Approximately 400 tons of Lurgi processed oil shale waste was provided by Rio Blanco Oil Shale Co., Inc. (RBOSC) through a separate cooperative agreement with the University of Wyoming (UW) to carry out this study. Three of the lysimeters were established at the RBOSC Tract C-a in the Piceance Basin of Colorado. Two lysimeters were established in the Environmental Simulation Laboratory (ESL) at UW. The ESL was specifically designed and constructed so that a large range of climatic conditions could be physically applied to the processed oil shale which …

Abstract: "The cross section for the reaction Al²⁷(p,3pn)Na²⁴ has been measured for proton energies between 30 and 350 Mev relative to the cross section for the reaction C12(p,3pn)C11, and the absolute magnitude determined by matching with data measured with a Faraday cup at 350 Mev and at 31.5 Mev."

Studies in the 321 Building dissolver during December 1953 and January 1954, were successful in developing a laboratory-proved mercury-catalyzed dissolving flowsheet into a suitable plant procedure. However, this flowsheet was not adapted for Redox plant operation because of uncertainty about the possible presence of hydrogen above the lower explosive limit in the off-gases. Subsequent laboratory work has resulted in a better understanding of the hydrogen evolution, and has resulted in developing low hydrogen evolution flowsheets. When one of these flowsheets is selected for further work, it will be tested in the 321 Building dissolver with non-irradiated slugs to provide information for scaling-up the single-slug laboratory data to a plant-scale operation. It is the purpose of this memorandum to outline the factors considered to be pertinent to the 321 Building investigation, to be used as a guide in making preparations for the runs to be performed.

The objective of this production test is to authorize the installation of at least 40 additional large size Zircaloy process tubes in graphite channels that have been enlarged to 2.275 inches at C Reactor and to charge these tubes with large diameter (CVIN) fuel elements to obtain preliminary conversion ratio data and further qualitative data regarding the irradiation behavior of large diameter fuel element designs.

The high heat content solids contained in Tank 241-C-106 are to be removed and transferred to Tank 241-AY-102 by sluicing operations, to be authorized under project W320. While sluicing operations are underway, the state of these tanks will be transformed from unagitated to agitated. This means that the partition fraction which describes the aerosol content of the head space will increase from IE-10 to IE-8 (see WHC-SD-WM-CN062, Rev. 2 for discussion of partition fractions). The head spare will become much more loaded with suspended material. Furthermore, the nature of this suspended material can change significantly: sluicing could bring up radioactive solids which normally would lay under many meters of liquid supernate. It is assumed that the headspace and filter aerosols in Tank 241-AY-102 are a 90/10 liquid/solid split. It is further assumed that the sluicing line, the headspace in Tank 241-C-106, and the filters on Tank 241-C-106 contain aerosols which are a 67/33 liquid/solid split. The bases of these assumptions are discussed in Section 3.0. These waste compositions (referred to as mitigated compositions) were used in Attachments 1 through 4 to calculate survey meter exposure rates per liter of inventory in the various system components. Three accident scenarios are evaluated: …

This report discusses the use of coal tar to extinguish potential magnesium fires in stored metal turnings at the Hanford Engineer Works. The report is dated August 11, 1943. (JL)

The report is divided into: Fissionable materials (2000 program): studies related to production reactors, studies related to separations plants; reactor development (4000 program): Studies related to plutonium recycle program.

In the development of fuel elements for the NPR, one potentially serious fuel element problem -- high temperature uranium swelling -- has not been experimentally investigated. A series of experiments has been proposed in which uranium fuel rod with different amounts of Zircaloy-2 cladding will be irradiated to high exposure at temperatures equivalent to those expected in an NPR. These experiments should show the importance of high temperature uranium swelling as a limiting factor in NPR fuel element behavior. To obtain sample rod temperature of 250 to 300{degree}C on the surface and 500 to 650{degree}C at the center, the rods will be irradiated in aluminum capsules loaded in standard reactor process tubes. The high temperatures will be obtained by restricting the heat flow from the uranium sample to the coolant. The purpose of this test is to determine the validity of the heat transfer calculations used in predicting the temperature drops within the capsule by irradiating one capsule at known flux conditions and measuring the temperature attained by the uranium rod sample. The data obtained from this test will be used in determining the irradiation conditions required for the full scale uranium swelling tests.

The present liquid third safety is considered undesirable for the piles at their present power levels. Any increase in power level and graphite temperature makes the need for an alternative third safety increasingly imperative. The use of the third safety is envisioned under conditions where the supply of cooling water to an operating pile is interrupted and concurrently the safety rods full to enter the pile because of slight shifting of the top shield or larger shifting of the winches, relative to the pile proper. Under these conditions, undesirable properties of a liquid third safety are present and are discussed in this memorandum.

Abstract: "This paper describes an electrical readout, decade counter employing the magnetron beam switching tube with transistor drive. Double pulse resolution is one microsecond. The unit will accept a variety of transistor types and will tolerate supply voltage variations of +/- 20% at ambient temperatures up to 60 C. A "Pixie" neon indicator is driven without the use of additional transistors. A readout circuit for printer on punched paper tape is presented."

This report gives results of a study of the effect of changes in axial power distribution on rupture potential. Possible interrelationships between this effect and the effects of other reactor variables were investigated.

This report covers the activities of the Geotechnical Board and its two national committees, the US National Committee for Rock Mechanics (USNC/RM) and the US National Committee on Tunneling Technology (USNC/TT), for the period from March 1, 1991 to June 30, 1992. The report covers a 16-month period, through June of this year, to bring the reporting period in line with the National Research Council`s (NRC) fiscal year. Subsequent reports will cover the 12-month period July 1--June 30, unless individual contracts require otherwise. A description of the Geotechnical Board and its committees within the context of the National Academy of Sciences/National Research Council, as well as lists of current members of the board and national committees can be found in Attachment A.

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A wireless link was designed using a patch antenna. In the process, several different models were tested. Testing proved a patch antenna was a viable solution for building a wireless link within the design specifications. Also, this experimentation provided a basis for future patch antenna design.

Recent measurements of the infrared (IR) absorption coefficient of CH and CD capsules differ significantly from earlier estimated values from thin flat samples. The optimum wavelength for IR enhanced layering of DT and D{sub 2} ice layers inside of a NIF scale hohlraum depends on the relative ice and capsule absorption coefficients. This update of a previous memo shows the maximum ice heating with IR as a function of ice and capsule absorption instead of at discrete wavelengths. Also discussed is the leverage of other parameters, such as the IR absorption of the hohlraum wall and thermal conductivities of the support rods and exchange gas. The most likely capsule and ice absorption values limit the IR heating to between 2-7 Q{sub DT}. We find most leverage of the IR heating comes from increasing the ice to capsule absorption ratio. As before, this is the conduction only limit to IR, with convection potentially playing a large role.

This report presents data and information that supports the groundwater module. The conceptual model of groundwater flow and transport at the Hanford Site is described and specific information applied in the numerical implementation module is provided.

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This report describes the selection of the relief valves for the D-Zero cryostats. The selection was based on the flow requirements calculated in D-Zero engineering note 3740.214,224-EN-6 under fire conditions (1200 F, no vacuum) for the central cryostat; 264 SCFM. This value was calculated from section 5.3.5 of 'Pressure Relief Device Standards; S 1.3-Compressed Gas Storage Containers', published by the Compressed Gas Association, Inc. The flow calculated above is far greater than the required fire condition flow capacity of 264 SCFM. The improbable 70 F flow temperature value of 738 SCFM is still much greater than the required fire capacity. The flow capacity of the paralleled supplemental rupture disc is 2640 SCFM, independently greater than the fire condition flow requirement.

Some estimates of the shape of C/sub s/ ion and C/sub s/ atom interaction potentials suggest that the C/sup +//sub s/ + C/sup +//sub s/ charge transfer cross section may be less than 10/sup -15/ cm/sup 2/.