Significant accomplishments completed during Phase III of the /sup 60/Co Heat Source Demonstration program include the following: encapsulation of 2 MCi of /sup 60/Co; fabrication of the heat source, including the ASME coded pressure vessel/core assembly, and biological shielding; endurance testing of a prototype heat pipe for a period of 28 months; fabrication and qualification of the heat pipe emergency cooling subsystem; issue of the safety evaluation report, reference 3, and the operations manual, reference 4; and heat source assembly. The planned demonstration test program was modified to include testing of a total power system. Based on an evaluation of available power conversion systems, which included the closed-cycle Brayton and organic Rankine systems, the closed-cycle Brayton system was selected for use. Selection was based on advantages offered by the direct coupling of this conversion system with the gas-cooled heat source. In implementing the test program, the AiResearch BCD power conversion system was to be coupled to the heat source following initial heat source performance testing and part way through the endurance test. In accordance with the program redirection the following Phase IV checkout operations were completed to evaluate procedural and hardware acceptability: heat source dummy fueling; fueling cask sielding survey; …

The generator developed for the Pioneer mission evolved from the SNAP 19 RTG's launched aboard the NIMBUS III spacecraft. In order to satisfy the power requirements and environment of earth-escape trajectory, significant modifications were made to the thermoelectric converter, heat source, and structural configuration. Specifically, a TAGS-2N thermoelectric couple was designed to provide higher efficiency and improved long term power performance, and the electrical circuitry was modified to yield very low magnetic field from current flow in the RTG. A new heat source was employed to satisfy operational requirements and its integration with the generator required alteration to the method of providing support to the fuel capsule.

Initial experimental work led to the award of the first AEC thermionic contract on May 1, 1962, for the development of fission heated thermionic cells with an operating life of 10,000 hours or more. Two types of converters were fabricated: (1) electrically heated, and (2) fission heated where the fuel was either uranium carbide or uranium oxide. Competition between GGA and GE was climaxed on July 1, 1970 by the award to GGA of a contract to develop an in-core thermionic reactor. This report is divided into the following: thermionic research, materials technology, thermionic fuel element development, reactor technology, and systems technology.

We propose a novel technique to study hadron-hadron collisions in which a significant fraction of the available energy is carried off in directions transverse to the beam. The technique is independent of the details of the final state so is ideally suited to searching for the jet-like particle clusters predicted by the parton model. The detector consists of a small calorimeter and several planes of 1 meter square proportional chambers.

The theoretical basis and computational procedure of the VECTRA computer program are presented. VECTRA (Vorticity-Energy Code for TRansport Analysis) is designed for applying numerical simulation to a broad range of intake/discharge flows in conjunction with power plant hydrological evaluation. The code computational procedure is based on finite-difference approximation of the vorticity-stream function partial differential equations which govern steady flow momentum transport of two-dimensional, incompressible, viscous fluids in conjunction with the transport of heat and other constituents.

A scanning electron microscope (SEM) facility for the examination of tritium-containing materials is operational at Mound Laboratory. The SEM is installed with the sample chamber incorporated as an integral part of an inert gas glovebox facility to enable easy handling of radioactive and pyrophoric materials. A standard SEM (ETEC Model B-1) was modified to meet dimensional, operational, and safety-related requirements. A glovebox was designed and fabricated which permitted access with the gloves to all parts of the SEM sample chamber to facilitate detector and accessory replacement and repairs. A separate console combining the electron optical column and specimen chamber was interfaced to the glovebox by a custom-made, neoprene bellows so that the vibrations normally associated with the blowers and pumps were damped. Photomicrographs of tritiated pyrophoric materials show the usefulness of this facility. Some of the difficulties involved in the investigation of these materials are also discussed. The SEM is also equipped with an energy dispersive X-ray detector (ORTEC) and a Secondary Ion Mass Spectrometer (3M) attachments. This latter attachment allows analysis of secondary ions with masses ranging from 1-300 amu.

Partial summary: "The drainage and erosion control facilities of 54 installations were observed to evaluate performance of surface and subsurface drainage systems, erosion control measures, and conditions of buried conduits and associated facilities. Although the facilities observed varied from only 1 to 30 years or more of age and it is recognized that basic demands have increased as well as the fact that design and construction procedures have been improved continuously, many of the old familiar problems still exist and a few new ones have developed" (p. xi).

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Analytic and Monte Carlo calculations of the Bramblett- Czirr /sup 235/U transmission experiment STANuc!. Sci. Eng. 35, 350-357 (1969)! were performed. The numbcr of fissions from the uncollided flux could be calculated as a function of depth. The results of experiment and Monte Carlo calculations are tabulated and plotted; fission and total cross sections for /sup 235/U are shown. In view of the agreement between the analytic and Monte Carlo calculations, it appeared that the ENDF/B-III cross sections were inadequate to calculate the Czirr-- Bramblett experiment. (3 figures, 2 tables) (RWR)

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Numerous experimental observations on the carburization-decarburization behavior of austenitic stainless steels in hightemperature flowing sodium have been reported; however, quantitative predictions of carbon diffusion in the steels under specific environmental conditions have been difficult. A mathematical analysis for the process has been developed that incorporates (1) the thermodynamic and kinetic information for carbon in the alloys, (2) the thermal-mechanical treatment of the material (solution annealed versus cold worked) that influences the microstructure, and (3) the carbon concentration in sodium and its dependence on sodium-system parameters. Carbon concentrationdistance profiles in Types 304 and 316 stainless steel were generated as a function of time, temperature, and carbon concentration in sodium and compared with experimental data. The analysis was used to evaluate the carburization -- decarburization behavior of Type 316 stainless steel fuel cladding exposed to sodium and to develop carbon-diffusion profiles in Type 304 stainless steel intermediate-heat-exchanger piping upon exposure to primary- and secondary-system sodium for periods to 30 y. (auth)

Current activities and technical progress for the period April through June 1973 are reported for two subtasks. Subtask A covers the planning and analysls of critical experiments in ZPPR-3. Subtask B progress is reported for nuclear data evaluation and testing and methods development in support of Subtask A. (auth)

Free-free absorption is one of the dominant mechanisms governing the absorption of laser radiation by materials heated to temperatures of 0.5 to 2.0 eV. This report describes the theory, the listing, and the running instructions for a code which computes the free-- free Gaunt factor, arising from any given ionic or atomic potential. The calculation makes use of partial wave expansion. The code is capable of computing up to 95 partial waves. The code computes the necessary low energy wave functions by making use of the Green's function solution rather than by directly integrating Schroedinger's equation. In addition to the Gaunt factor, the code also provides the amplitude and the phase shift of every partial wave considered. (auth)

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Overall heat-transfer coefficients were obtained in a single-tube loop for a smooth tube and two fluted tubes proposed for use in a geothermal brine upflow VTE pilot plant. Tests were run at steam temperatures from 250 to 390 deg F, flow rates of 0.5 to 2.5 gpm, and steam to brine DELTA Ts of 10 to 30 deg F using demineralized water and 3% NaCl solutions. In each case the liquid entering the tube flashed through a DELTA T equal to the steam- brine DELTA T. The tubes tested were a 3/4-in. smooth stainless steel tube, a 1-in. double- fluted CuNi tube, and a 7/8-in. double-fluted Al brass tube. Average heat transfer coefficients using 3% NaCl were as follows: for the stainless steel tube, 550 Btu/hr/ deg F/ft/sup 2/ at 250 to 765 at 390 deg F; for the CuNi tube, 2000 at 250 to 2600 at 390 deg F; for the aluminum brass tube, 1750 at 250 deg to about 2650 at 390 deg F. Flow rate and DELTA T, in general, had only small effects on the coefficients. (auth)

High magnetic fields render the semimetal bismuth sufficiently transparent at far infrared frequencies to study effects not previously seen in reflection experiments. The frequency interval 10 to 400 cm/sup -1/ was explored at fields up to 100 kG using Fourier transform spectroscopic techniques and /sup 3/He-cooled bolometer detectors, and samples were cooled to liquid helium temperatures. Transmission was observed in all three principal crystal direc:. tions when the magnetic field was sufficiently large to drive one or more sets of electrons into the extreme quantum limit. The reduced absorptivity at these fields results from a large reduction in the relaxation rate. (35 figures, 49 references) (DLC)

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In contrast to earlier editions, which presented in compact form a summary of the complete store of the neutron data files, this edition aims to provide those portions of neutron data considered to be of prime importance and best suited for inclusion in ready reference form. This volume contains thermal cross sections, resonance properties, resonance parameters, and bibliography for nuclides from H to /sup 257/Fm. Notation and nomenclature, considerations involved in the recommendations, and a table of energyordered resonances are also included. (RWR)

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