This paper contains lecture notes given by Gary Feinberg on the historical aspect of the violation of P and C invariance and more recently the violation of CP invariance. (LSP) 13 refs., 2 figs., 2 tabs.

The preliminary safety assessment report analyzes the potential radiological risk of the integrated MSNPS with the launch vehicle including interface with the weapon system. Most emphasis will be placed the prime power concept design. Safety problems can occur any time during the entire life cycle of the system including contingency phases. The preliminary safety assessment report is to be delivered at the end of phase 2. This assessment will be the basis of the safety requirements which will be applied to the design of the MSNPS as it develops in subsequent phases. The assessment also focuses design activities on specific high-risk scenarios and missions that may impact safety.

The Phase 2 program objectives are to (1) demonstrate concept feasibility, (2) develop a preliminary design, and (3) complete Phase 3 engineering development and ground test plans. The approach to accomplish these objectives is to prove technical feasibility of our baseline design early in the program while maintaining flexibility to easily respond to changing requirements and advances in technology. This approach recognizes that technology is advancing rapidly while the operational phase MSNPS is 15 to 20 years in the future. This plan further recognizes that the weapons platform and Advanced Launch System (ALS) are in very early program definition stages; consequently, their requirements, interfaces, and technological basis will evolve. This document outlines the Phase 2 plan along with task scheduling of the various program aspects.

This meeting was held at Oak Ridge National Laboratory on March 17, 1989, to review the technical progress on the collaborative DOE/JAERI program on fusion reactor materials. The purpose of the program is to determine the effects of neutron irradiation on the mechanical behavior and dimensional stability of US and Japanese austenitic stainless steels. Phase I of the program focused on the effects of high concentrations of helium on the tensile, fatigue, and swelling properties of both US and Japanese alloys. In Phase II of the program, spectral and isotropic tailoring techniques are fully utilized to reproduce the helium:dpa ratio typical of the fusion environment. The Phase II program hinges on a restart of the High Flux Isotope Reactor by mid-1989. Eight target position capsules and two RB* position capsules have been assembled. The target capsule experiments will address issues relating to the performance of austenitic steels at high damage levels including an assessment of the performance of a variety of weld materials. The RB* capsules will provide a unique and important set of data on the behavior of austenitic steels irradiated under conditions which reproduce the damage rate, dose, temperature, and helium generation rate expected in the first wall …

A platform to be used for the installation and repair of the high voltage pre-amp boxes on the CC cryostat has been designed to support a uniform load of 30 Ibs./sq. ft. However, according to the standards set by both the American National Standard and the Uniform Building Code, the minimum uniformly distributed design load for a structure used as an 'elevated platform or walkway' is 60 lbs./sq. ft. The existing platform was tested with a uniform load of 40 lbs./sq. ft. with no major problems occurring during the testing. Considering a 40 lbs./sq. ft. load to be the minimum acceptable value for 'residential' use, and the platform in hand to be better categorized as an 'elevated platform or walkway', the platform is carefully re-analyzed for a 60 lbs./sq. ft. uniformly distributed load.

This report is in three parts, though each is briefly described data is provided. The three parts address (1) radioiodination of human thrombin and fibrinogen; (2) interaction of blood components with ultra- smooth polymer surfaces; and (3) initial studies of Tecoflex and treated Tecoflex cups with normal serum samples.

This Specification establishes the performance, design, development, and test requirements for the Boeing Multimegawatt Space Nuclear Power System (MSNPS). The Boeing Multimegawatt Space Power System is part of the DOE/SDIO Multimegawatt Space Nuclear Power Program. The purpose of this program is to provide a space-based nuclear power system to meet the needs of SDIO missions. The Boeing MSNPS is a category 1 concept which is capable of delivering 10's of MW(e) for 100's of seconds with effluent permitted. A design goal is for the system to have growth or downscale capability for other power system concepts. The growth objective is to meet the category 3 capability of 100's of MW(e) for 100's of seconds, also with effluent permitted. The purpose of this preliminary document is to guide the conceptual design effort throughout the Phase 1 study effort. This document will be updated through out the study. It will thus result in a record of the development of the design effort.

At high coverage, sulfur generally deactivates metal catalysts, but at low coverage, chemisorbed sulfur can have a more subtle effect on catalyst activity and selectivity. The general goal of the current project is to examine fundamental aspects of selective poisoning by fractional monolayers of chemisorbed sulfur on a variety of metal catalysts used for commercially important reactions such as hydrocarbon re-forming, light alkane steam re-forming, and hydrocarbon synthesis. Specific objectives of the research program are to experimentally measure as a function of coverage the influence of chemisorbed sulfur on the thermodynamics, reactivity, and structure of surface and bulk carbon occupying both dispersed and well-characterized metal catalyst surfaces. Special methods, such as reversible sulfur chemisorption on supported metals and temperature-programmed reaction (TPR) characterization of catalyst carbon, have been developed that are well suited to examining the interaction of sulfur and carbon on metal surfaces. New analytical instruments with greatly improved sensitivity have been recently developed and applied: a helium discharge ionization detector (DID) is being used with a gas recirculation thermodynamic system, and the surface analysis by laser ionization (SALI) technique is used with surface carbon segregation systems.

Continuing investigations of multiphoton ionization processes in naphthalene have established the geometry and spectroscopy of trimer and tetramer cluster states. A new, highly efficient ionization mechanism has been identified in the trimer. It is closely related to autoionization of 2-electron atoms by resonant 2-photon excitation and to exciton fusion in larger clusters.

This is the final report on the geothermal analysis and evaluation for the proposed nuclear waste repository at Yucca Mountain, for the period of July 1, 1989 to December 31, 1989. Heat flow values were derived by measuring the thermal conductivities of samples taken from selected exploratory wells. Temperature gradients are recorded from the same wells. By using computer generated contour maps of the area, another interpretation of the heat-flow can be derived. Results of the mapping do not coincide with the past observations of the data. Another method used to evaluate the heat-flow of Yucca Mountain was to compare the temperature-depth relationship of the area. (MB)

The cold support concept for the ARIES TF coil design was developed further. This concept not only works for aspect ratio 6 and 4.5 machines, but it also works for ITER. Beryllium was added to the two blanket concepts to improve energy multiplication and reduce COE. During the quarter a US-Japan steering committee meeting was held to discuss the US-Japan ICRH tube tests. They reviewed and approved the proposed X2242 ICRH tube improvements. Ed Cheng attended IAEA meeting on the International Fusion Evaluated Nuclear Data Library (FENDL). The first version of FENDL should be ready for use by mid-1990. Exposure of 12 well-characterized graphite tiles in the divertor region of DIII-D continues. Work has been initiated on the laser ellipsometry technique to be used for in situ on-line measurement of erosion and redeposition in the DIII-D divertor. A Neutron Interaction materials (NIM) report has been drafted compiling published and unpublished data on manganese-stabilized austenitic steels. These steels are being considered for the ITER.