Richard Q Wright
Oak Ridge National Laboratory
Network
Latest external collaboration on country level. Dive into details by clicking on the dots.
Publication
Featured researches published by Richard Q Wright.
Archive | 2013
Julian K. Benz; Thomas Lillo; Richard Q Wright
Alloy 617 has been selected as the primary candidate for heat exchanger applications in advanced reactors. For the VHTR this application could require extended service up to a reactor outlet temperature of 950°C. A key hurdle to using this alloy in the VHTR heat exchanger application is qualifying the alloy for Section III of the ASME Boiler and Pressure Vessel Code. In order to Code qualify the material it is necessary to characterize the influence of long term aging on the mechanical behavior. Alloy 617 has been aged at 650 and 750°C for times up to 5300 hours. The microstructure after aging has been characterized using optical and transmission electron microscopies. It has been determined that in addition to carbides, a significant volume fraction of ?’ phase (Ni3Al) is formed at these temperatures. The ?’ does not contribute significantly to changing the tensile or impact properties of the aged material. It does, however, appear to increase creep resistance and impede creep crack growth.
Transactions of the american nuclear society | 1995
C.V. Parks; W. C. Jordan; L. M. Petrie; Richard Q Wright
Archive | 2014
Richard Q Wright; Michelle C. Brady-Raap; Robert Michael Westfall
Transactions of the american nuclear society | 2010
Robert Michael Westfall; Richard Q Wright
Archive | 2009
Robert Michael Westfall; Richard Q Wright
Transactions of the american nuclear society | 1999
Richard Q Wright; W.C. Jordan; Luiz C Leal
Transactions of the american nuclear society | 1995
M.L. Williams; M. Asgari; Richard Q Wright
Transactions of the american nuclear society | 2010
Richard Q Wright; Laura Carroll; Cabet Celine
Archive | 2010
Laura Carroll; Julian K. Benz; Richard Q Wright
Archive | 2009
Robert Michael Westfall; Richard Q Wright