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Westinghouse submits AP1000 design revision to NRC
Yesterday, the Nuclear Regulatory Commission announced that it has received an application from Westinghouse to renew and update the design certification (DC) for its AP1000 reactor. This application seeks to formally incorporate the lessons learned from the construction of Vogtle-3 and -4 into the design control document (DCD) of the AP1000.
This long-expected submittal builds on previous plans at both the NRC and Westinghouse for the future of gigawatt-scale light water reactor deployments in the United States.
Kunihiko Tsuchiya, Hideki Imaizumi, Hiroshi Kawamura, Rokuro Oyamada, Toshiyuki Kabutomori, Yuichi Wakisaka
Fusion Science and Technology | Volume 28 | Number 3 | October 1995 | Pages 1431-1436
Tritium Storage, Distribution, and Transportation | Proceedings of the Fifth Topical Meeting on Tritium Technology In Fission, Fusion, and Isotopic Applications Belgirate, Italy May 28-June 3, 1995 | doi.org/10.13182/FST95-A30613
Articles are hosted by Taylor and Francis Online.
An in-situ irradiation test of a fusion blanket is planned in JMTR (Japan Materials Testing Reactor) using lithium containing ceramics as the tritium breeder and beryllium as the neutron multiplier. Therefore, it is necessary to develop getters for the recovery of the tritium gas. In this study, Zr9Ni11 alloy was chosen as a getter, and pressure-composition isotherms between 20°C and 300°C, and other properties were measured for its application. The breakthrough test of hydrogen was carried out with Ar+H2 gas. The evaluation of the examined getter materials leads to the conclusion that the Zr9Ni11 alloy may be used for the in-situ irradiation test of fusion blanket.
