his only naming convention and can use free format input. This paper will also be concerned with the solution procedures available. The systems code uses Powell's hybrid method for solving N-dimensional nonlinear equations and Brent's method for a 1-dimensional equation. Powell's variable metric constrained method is used for N-dimensional non-linear optimization and Brent's method for the optimization of one variable. This systems code (SALT) has been written to be used as an evolving analysis tool rather than a definitive encompassing code. It is easy to modify the code (which is completely modularized) to meet particular needs, especially to include the users component models which may be of interest to him. Title: Uncertainties in thermal-structural analysis of large space structures Source: Proceedings of the AFOSR Special Conference on Prime-Power for High Energy Space Systems, Norfolk, Virginia, USA, Feb. 22-25, 1982. (Paper No. X-9) Authors: Thornton, Earl A.; <Mech. Engineering and Mechanics Dept., Old Dominion University, Norfolk, VA 23508> Date: 02-22-82 Classification: u Keywords: structure and design Abstract: Uncertainties in the thermal-structural analysis of large space structures are briefly described. Thermal-structural design challenges faced by structural engineers are highlighted. Some basic questions arising in predictive analyses are identified and illustrated with recent research. Areas ATTACHMENT : for further research are discussed, and the need for fundamental thermal-structural experiments is cited. Title: Thermionic conversion for space power application Source: Proceedings of the AFOSR Special Conference on Prime-Power for High Energy Space System, Norfolk, Virginia, USA, Feb. 22-25, 1982. (Paper No. IX-1) Authors: Yang, L.; Fitzpatrick, G. ; Date: 02-22-82 Classification: u Keywords: alternative systems, nuclear, space energy conversion Abstract: Extensive efforts were made during 1960 to 1980 to develop thermionic conversion for space power application. Between 1960 and 1972, the efforts were devoted to the development of in-core thermionics. Tungsten, niobium and Al 0 ATTACHMENT : were selected as the emitter, collector, and insulator materials for the converter. Uranium carbides and uranium oxide were selected as candidates for the nuclear fuel. A total of 36 fueled thermionic converters and fuel elements were life-tested during 1965 to 1972. These tests, supported by a dozen of out-of-pile converter tests and several material irradiation tests, provided the base of the in-core thermionic technology. Unfueled converter has demonstrated a life of five years or more, while fueled converters and fuel elements have been operated for one to one and one-half years. The major limiting factors for converter life and performance were fuel component diffusion through cladding and emitter swelling for the ox ide-fueled carbide™ fueled converters. Various means for mitigating the fuel effects on converter life and performance were proposed but they were not thoroughly evaluated before the in-core thermionic program was terminated at the beginning of 1973. Between 1973 and 1980, some limited efforts were made? to replace the in- core thermionic with out-of-core thermionics in order to eliminate the undesirable fuel effects on converter life and performance. Various approaches
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