Zobrazeno 1 - 10
of 29
pro vyhledávání: '"FA Garner"'
The precipitates that develop in AISI 316 stainless steel during irradiation play a dominant role in determining the dimensional and mechanical property changes of this alloy. This role is expressed primarily in a large change in matrix composition t
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2d3a6d44f9a4e27010c72b12c87a4a0f
https://doi.org/10.1520/stp28230s
https://doi.org/10.1520/stp28230s
As part of a larger effort to study the influence and possible synergisms involving solutes, helium and cold working, a simple quaternary alloy representing AISI 316 without solutes was irradiated in the Oak Ridge Research Reactor (ORR). This alloy's
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::4ca81b23d8a02fad93e5383fb86817b2
https://doi.org/10.1520/stp34344s
https://doi.org/10.1520/stp34344s
Autor:
FA Garner, JM McCarthy
A series of model Fe-Cr-Mn alloys and various solute-modified high manganese alloys have been irradiated in the Fast Flux Test Facility in order to provide an early assessment of the consequences of substituting manganese for nickel in austenitic sta
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::7f9e7e5caf0a20bd3d8e3e264d0885ad
https://doi.org/10.1520/stp24946s
https://doi.org/10.1520/stp24946s
This paper derives the relationships between void swelling and irradiation creep due to Stress-Induced Preferred Absorption (SIPA) and SIPA-Induced Growth (SIG) under cascade damage conditions in an irradiated pressurized tube. It is found that at lo
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b7ebd10b16a362afead98c6f41221e78
https://doi.org/10.1520/stp23925s
https://doi.org/10.1520/stp23925s
Variability of Irradiation Creep and Swelling of HT9 Irradiated to High Neutron Fluence at 400–600°C
Autor:
FA Garner, MB Toloczko
Sets of pressurized tubes constructed from a combination of three lots of HT9 and two heat-treatments were examined after irradiation in FFTF-MOTA at four different temperatures between 400 and 600 C. Diametral measurements indicated that small amoun
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::24c25c31c4ecd71b23e0b4198d1bad48
https://doi.org/10.1520/stp13902s
https://doi.org/10.1520/stp13902s
Irradiation-assisted stress corrosion cracking (IASCC) is a significant materials issue for the light water reactor (LWR) industry and may also pose a problem for fusion power reactors that will use water as coolant. A new metallurgical process is pr
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::abed2494b39285279cdba398e01b6671
https://doi.org/10.1520/stp13894s
https://doi.org/10.1520/stp13894s
It has recently been proposed that the unequal attenuation of {gamma}-rays and fast neutrons in the water gaps of boiling water reactors may lead to a significant underprediction of the atomic displacement rate at the pressure vessel wall. Since a la
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::758adfb1c9efda9ec5a1df42670abf4d
https://doi.org/10.1520/stp13857s
https://doi.org/10.1520/stp13857s