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The numerical methods used in the full particle-orbit following SPIRAL code are described and a number of physics studies performed with the code are presented to illustrate its capabilities. The SPIRAL code is a test-particle code and is a powerful numerical tool to interpret and plan fast-ion experiments in Tokamaks. Gyro-orbit effects are important for fast ions in low-field machines such as NSTX and to a lesser extent in DIII-D. A number of physics studies are interlaced between the description of the code to illustrate its capabilities. Results on heat loads generated by a localized error-field on the DIII-D wall are compared to measurements. The enhanced Triton losses caused by the same localized error-field are calculated and compared to measured neutron signals. MHD activity such as tearing modes and Toroidicity-induced Alfven Eigenmodes (TAEs) have a profound effect on the fast-ion content of Tokamak plasmas and SPIRAL can calculate the effects of MHD activity on the confined and lost fast-ion population as illustrated for a burst of TAE activity in NSTX. The interaction between Ion Cyclotron Range of Frequency (ICRF) heating and fast ions depends solely on the gyro-motion of the fast ions and is captured exactly in the SPIRAL code. …

Projection Gas Immersion Laser Doping (P-GILD) is an innovative doping process that utilizes finely patterned excimer laser light to thermally process discreet regions within an integrated circuit. By reducing the total temperature cycle to nanoseconds and localizing the thermal energy in depth and area, P-GILD fundamentally changes the junction formation process. This paper first reviews the general characteristics of the P-GILD process and equipment. Two variations of the technique, melt and non-melt, and their resulting junction characteristics are then described in detail. The combination of the two laser processes along with the simplification that a resistless technology brings to the process sequence, enables efficient fabrication of impurity profiles that are ideal for a wide array of transistor applications.

Memorandum - Minutes of the Infrastructure Evaluation Group (IEG). Including meeting agenda, a report, and any other additional information from the meeting.

Memorandum - Minutes of the Infrastructure Evaluation Group(IEG). Including meeting agenda, a report, and any other additional information from the meeting.

Memorandum - Minutes of the Infrastructure Evaluation Group (IEG). Including meeting agenda, a report, and any other additional information from the meeting.

Memorandum - Minutes of the Infrastructure Evaluation Group(IEG). Including meeting agenda, a report, and any other additional information from the meeting.

Memorandum - Minutes of the Infrastructure Evaluation Group(IEG). Including meeting agenda, a report, and any other additional information from the meeting.

A synthetic magnetic diagnostics code for fusion equilibria is presented. This code calculates the response of various magnetic diagnostics to the equilibria produced by the VMEC and PIES codes. This allows for treatment of equilibria with both good nested flux surfaces and those with stochastic regions. DIAGNO v2.0 builds upon previous codes through the implementation of a virtual casing principle. The codes is validated against a vacuum shot on the Large Helical Device where the vertical field was ramped. As an exercise of the code, the diagnostic response for various equilibria are calculated on the Large Helical Device (LHD).

Memorandum - Minutes of the Infrastructure Evaluation Group(IEG). Including meeting agenda, a report, and any other additional information from the meeting.

"Approximately 2,000 flights of rocket-propelled models have been made in which model configuration, model size, type and number of booster rockets, number of booster stages, and booster arrangements varied. A brief summary of the results obtained with some of the more unusual arrangements, descriptions of boosting hardware and techniques, and discussions of some factors responsible for the choice of these configurations are presented in this paper. The results show that unconventional boosting techniques may be used successfully when conventional tandem arrangements are unsuitable or unwieldy" (p. 1).

Memorandum - Minutes of the Infrastructure Evaluation Group(IEG). Including meeting agenda, a report, and any other additional information from the meeting.

The objective of the vadose zone characterization under this program is to develop a better conceptual geohydrologic model of identified tank farms which will be characterized so that threats to human health and the environment from past leaks and spills, intentional liquid discharges, potential future leaks during retrieval, and from residual contaminants that may remain in tank farms at closure can be explicitly addressed in decision processes. This model will include geologic, hydrologic, and hydrochemical parameters as defined by the requirements of each of the TWRS programs identified here. The intent of this TWRS Vadose Zone Program Plan is to provide justification and an implementation plan for the following activities: Develop a sufficient understanding of subsurface conditions and transport processes to support decisions on management, cleanup, and containment of past leaks, spills, and intentional liquid discharges; Develop a sufficient understanding of transport processes to support decisions on controlling potential retrieval leaks; Develop a sufficient understanding of transport processes to support decisions on tank farm closure, including allowable residual waste that may remain at closure; and Provide new information on geotechnical properties in the 200 Area to supplement data used for design and performance assessment for immobilized low-activity waste disposal facilities.

In May, 1961, it waa determined no renewed nuclear reaction in the SL-1 pressure vessel was possible as long as water was excluded. It was therefore possible to proceed with the final phase of the SL-1 recovery. This work consisted of moving the pressure vessel and core to the Hot Shop at the north end of the National Reactor Testing Station, dissecting and analyzing the reactor and its components, cutting up and burying the reactor building, and decontaminating the rest of the SL-1 area. These things were accomplished by the General Electric Company between May 1961 and July 1962. It was determined that the central control rod was bound in its shroud at a position corresponding to 20- inch withdrawal. Analysis of the pertinent data showed that the amount of reactivity associated with this rod position, inserted at a rate compatihie with manual withdrawal of the rod, can explain the significant evidence which was coliected. No other means of withdrawing the rod was found to be in accordance with the evidence. It was found that the relatively low yield (130 Mw-sec) nuclear excursion produced a water hammer with pressures up to 10,000 psi, which, in turn, caused the pressure vessel …