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Commercial nuclear innovation "new space" age
In early 2006, a start-up company launched a small rocket from a tiny island in the Pacific. It exploded, showering the island with debris. A year later, a second launch attempt sent a rocket to space but failed to make orbit, burning up in the atmosphere. Another year brought a third attempt—and a third failure. The following month, in September 2008, the company used the last of its funds to launch a fourth rocket. It reached orbit, making history as the first privately funded liquid-fueled rocket to do so.
Satoshi Konishi, T. Nagasaki, T. Hayashi, K. Okuno
Fusion Science and Technology | Volume 26 | Number 3 | November 1994 | Pages 668-672
Plasma Fueling and Fuel Cycle | Proceedings of the Eleventh Topical Meeting on the Technology of Fusion Energy New Orleans, Louisiana June 19-23, 1994 | doi.org/10.13182/FST94-A40234
Articles are hosted by Taylor and Francis Online.
Behavior and improvement of the ZrCo based intermetallic materials for tritium recovery, storage and supply are studied. Compound ZrCo was found to be subject to disproportionation at high temperature under high hydrogen pressure to form ZrCo2 and ZrH2. This process is completely reversed by vacuum treatment at temperature above 500°C for several hours. Kinetics of the disproportionation was described to be similar to phase transition that have apparent incuvation time to take place. The logarithmic reaction rate constant was related to the reciprocal temperature. With some precautions drawn from the results, this reaction is not a problem in practice. For the application that needs prolonged supply of relatively high-pressure tritium, solid solution of ZrCo and HfCo was developed as an improvement of the material. Materials otained by arc melting with compoistion of Zr(1−x)HfxCo (0<x<0.5) exhibits single plateaus in pressure - composition isotherms when hydrogenated. Repeated hydrognation - dehydrogenation cycles did not generate separate ZrCo and HfCo phases. The equilibrium hydrogen pressure in the plateau regions are expressed as a functio of reciprocal temperature and increases with increasing HfCo contents. This material provides controlled equilibrium hydrogen pressure required for specific applications of tritium storage nad supply.
