The objective of this project is the development of a preliminary design for a full-sized, closed cycle, ammonia power system module for the 100 MWe OTEC Demonstration Plant. In turn, this Demonstration Plant is to demonstrate, by 1984, the operation and performance of an ocean thermal power plant having sufficiently advanced heat exchanger design to project economic viability for commercial utilization in the late 1980's and beyond. Included in this power system development are the preliminary designs for a proof-of-concept pilot plant and test article heat exchangers which are scaled in such a manner as to support a logically sequential, relatively low-cost development of the full-scale power system module. The conceptual designs are presented for the Demonstration Plant power module, the proof-of-concept pilot plant, and for a pair of test article heat exchangers. Costs associated with the design, development, fabrication, checkout, delivery, installation, and operation are included. The accompanying design and producibility studies on the full-scale power system module project the performance/economics for the commercial plant. This section of the report describes the full-size power system module, and summarizes the design parameters and associated costs for the Demonstration Plant module (prototype) and projects costs for commercial plants in production. The …

The LOFT Primary System Motor Generator Set was analyzed for sliding and overturning during a seismic event. The assembly is located in TAN 650, Room B239, and is satisfactory against seismic loading.

A preliminary feasibility study of solvent extraction methods has been completed for removing actinides from selected salt wastes likely to be produced during reactor fuel fabrication and reprocessing. The use of a two-step solvent extraction system, tributyl phosphate (TBP) followed by a bidentate organophosphorus extractant (DHDECMP), appears most efficient for removing actinides from salt waste. The TBP step would remove most of the plutonium and >99.99% of the uranium. The second step, using DHDECMP, would remove >99.91% of the americium, the remaining plutonium (>99.98%), and other actinides from the acidified salt waste.

A stress analysis of the LOFT Diesel Generator ''A'' Exhaust Stack was performed to determine its reaction to Safe-Shutdown Earthquake loads. The exhaust stack silencer and supporting foundation was found to be inadequate for the postulated seismic accelerations. Lateral support is required to prevent overturning of the silencer pedestal and reinforcement of the 4'' x 0.5'' silencer base straps is necessary. Basic requirements for this additional support are discussed.

Construction of the Shiva laser system is nearing completion. This laser will be operating in fall 1977 and will produce over 20 terawatts of focusable power in a subnanosecond pulse. Fusion experiments will begin early in 1978. It is anticipated that thermonuclear energy release equal to one percent that of the incident light energy will be achieved with sub-millimeter deuterium-tritium targets. From other experiments densities in excess of a thousand times that of liquid are also expected.

The creep deformation and rupture of type 304/308 stainless steel structural weldments at 593/sup 0/C (1100/sup 0/F) was experimentally investigated to study the comparative behavior of the base metal and weld metal constituents. The tests were conducted in support of ORNL's program to develop high-temperature structural design methods applicable to liquid-metal fast breeder reactor (LMFBR) system components that operate in the creep range. The specimens used were thin-walled, right circular cylinders capped with either flat or hemispherical heads and tested under internal gas pressure. Circumferential welds were located in different regions of the cylinder or head and, with one exception, were geometrically duplicated by all base metal regions in companion specimens. Results are presented on the comparative deformation and rupture behavior of selected points in the base metal and weldment regions of the different specimens and on the overall surface strains for selected specimens.

Differential cross sections for incoherent scattering by K-shell electrons were measured, using coincidence techniques, for incident photons having energies of 662 keV, 320 keV, and 145 keV. The spectral distributions of the scattered photons emerging at scattering angles from 20/sup 0/ to about 140/sup 0/ are reported. Target materials were iron, tin, holmium, and gold at 320 keV; tin and gold at 662 keV; and iron and tin at 145 keV. A typical energy spectrum consists of a scattered peak that is much narrower than would be expected from the bound state electron motion. The peak also, typically, reaches a broad maximum width for scattering angles between 45/sup 0/ and 60/sup 0/. Rather than monotonically increasing with atomic number the peak width reaches a broad maximum, generally, between Z = 50 and Z = 67, and then decreases with increasing atomic number. No Compton defect appears in any of the peaks to within +- 20 keV. A discussion of the expected magnitude of the Compton defect is included. The peak is superimposed on a continuum that diverges at the low end of the scattered photon spectrum for the following cases: gold, holmium, and tin targets for 320-keV incident photons; gold …

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This LTR documents LOFT Plant operational, upset, and emergency transients, and pressure and temperature conditions as generated by the LOFT Plant Dynamic analysis model of the primary system for use in steam generator specification. The results of this LTR have been supplemented by succeeding efforts as follows: FSAR analysis - (a) loss of load during full power operation, (b) loss of primary pump electrical power, and (c) loss of site power; and LOFT maneuvering analysis - (a) +-10% step change in steam flow, and (b) manual reactor trip. The initial plant conditions considered may differ from this LTR plant conditions. Items are outlined to document in this LTR other analyses which cover the same plant transients. 53 figs., 1 tab.

The fission product inventory, fission product release fractions, and radiation levels following a blowdown into the test chamber are presented. Operating sequences discussed are based on present knowledge and are used for the purpose of calculating radiation levels at different times.

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