Zobrazeno 1 - 10
of 22
pro vyhledávání: '"A.G. Hins"'
Publikováno v:
Journal of Nuclear Materials. 239:61-79
Irradiation-assisted stress corrosion cracking (IASCC) of several types of BWR field components fabricated from solution-annealed austenitic stainless steels (SSs), including a core internal weld, were investigated by means of slow-strain-rate test (
Publikováno v:
Journal of Nuclear Materials. 211:1-10
An isothermal diffusion couple between pure uranium and a uranium-27 at% plutonium alloy was annealed at 750°C for 25 h. Composition profiles were determined from electron microanalyses, from which interdiffusion fluxes and interdiffusion coefficien
Slow-strain-rate tensile tests and microstructural analysis by Auger electron spectroscopy were conducted on specimens of high- and commercial-purity (HP and CP) heats of Type 304 stainless steel obtained from neutron absorber tubes and a control bla
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::0b48cbb14cf0def45c794b97f7eed1bf
https://doi.org/10.1520/stp23976s
https://doi.org/10.1520/stp23976s
Autor:
D. J. Gavenda, H. M. Chung, T. F. Kassner, W. K. Soppet, W. J. Shack, O.K. Chopra, A.G. Hins, W.E. Ruther
This report summarizes work performed by Argonne National Laboratory on fatigue and environmentally assisted cracking (EAC) in light water reactors (LWRS) from October 1994 to March 1995. Topics that have been investigated include (a) fatigue of carb
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ae630be741ff7837f52813b41470095f
https://doi.org/10.2172/205937
https://doi.org/10.2172/205937
Autor:
A.G. Hins, R.G. Clemmer, J.R. Summers, L.R. Greenwood, J.R. Krsul, Richard F. Mattas, Victor A. Maroni, M.M. Hall, Yousry Gohar, R.L. Senn
Publikováno v:
Journal of Nuclear Materials. 118:275-285
A specimen of Li 7 Pb 2 (lithium in natural abundance) contained in a Zircaloy capsule was irradiated in the Oak Ridge Research Reactor Poolside Facility for ~ 700 h. The design of the irradiation assembly (designated TBC-07) permitted operational co
Publikováno v:
Journal of Nuclear Materials. :608-611
An alloy fabrication program has been initiated at Argonne National Laboratory to provide suitable materials for the evaluation of vanadium base alloys in the United States Fusion Power Program. The initial phase of the work has focused on the VCr