Zobrazeno 1 - 10
of 75
pro vyhledávání: '"Martin L Grossbeck"'
Publikováno v:
Journal of Nuclear Materials. 392:364-370
Thermal tests exposed V–4Cr–4Ti in static liquid lithium at 700 and 800 °C for 250, 500, and 1000 h. Post-exposure examination included chemical analysis of interstitial impurities in V–4Cr–4Ti to monitor impurity transfer, and tensile tests
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::54ff96dba807b04ed64aa2c8d4f05b53
https://doi.org/10.1016/j.jnucmat.2009.03.026
https://doi.org/10.1016/j.jnucmat.2009.03.026
Autor:
Martin L Grossbeck, Steven J. Zinkle, Richard J. Kurtz, Arthur F. Rowcliffe, Meimei Li, David T. Hoelzer
Publikováno v:
Journal of Nuclear Materials. :618-621
The paper presents irradiation creep data for V–4Cr–4Ti irradiated to 3.7 dpa at 425 and 600 °C in the HFIR-17J experiment. Creep deformation was characterized by measuring diametral changes of pressurized creep tubes before and after irradiatio
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::e42e40d786d160274d4cd22d8053f9c4
https://doi.org/10.1016/j.jnucmat.2008.12.220
https://doi.org/10.1016/j.jnucmat.2008.12.220
Autor:
Manoru Narui, Hideki Matsui, Takeo Muroga, Ken-ichi Fukumoto, Steven J. Zinkle, Meimei Li, Takuya Nagasaka, Martin L Grossbeck, David T. Hoelzer
Publikováno v:
Journal of Nuclear Materials. :788-793
This paper presents biaxial thermal creep results for the vanadium alloy V4Cr4Ti in liquid lithium using US Heat 832665 and two batches of tubing made from NIFS-Heat-2. The tests were performed at 700 and 800 °C over a stress range of 30–120 MPa u
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::e5cad86fc69188875f43853199482d53
https://doi.org/10.1016/j.jnucmat.2007.03.081
https://doi.org/10.1016/j.jnucmat.2007.03.081
Autor:
S.W. Kim, Akira Kohyama, Kiyoyuki Shiba, Martin L Grossbeck, Tomotsugu Sawai, Yutaka Kohno, Meimei Li, Hiroyasu Tanigawa, M. Ando
Publikováno v:
Journal of Nuclear Materials. :122-126
The irradiation creep behavior of F82H and several variants of JLF-1 steel has been measured at 573 and 773 K up to 5 dpa using helium-pressurized creep tubes irradiated in HFIR. These tubes were pressurized with helium to hoop stress levels of 0–4
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::39ac3b0e0d80163462a18797f6bf2450
https://doi.org/10.1016/j.jnucmat.2007.03.157
https://doi.org/10.1016/j.jnucmat.2007.03.157
Publikováno v:
Nuclear Fusion. 46:618-625
Vanadium alloys, candidate fusion reactor blanket materials, consist of intrinsic low activation elements for 14 MeV fusion neutrons (e.g. vanadium, chromium and titanium). From 500 to 1000 K, the tensile strength of vanadium alloys is independent of
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::41fe77890688e549a93d68bf3295daa1
https://doi.org/10.1088/0029-5515/46/5/012
https://doi.org/10.1088/0029-5515/46/5/012
Autor:
Hideki Matsui, David T. Hoelzer, Takuya Nagasaka, Takeo Muroga, Martin L Grossbeck, Steven J. Zinkle, Meimei Li
Publikováno v:
Fusion Engineering and Design. 81:307-313
A candidate low activation vanadium (V) alloy, V–4Cr–4Ti (NIFS-HEAT-2), was exposed to liquid lithium (Li) at 973 and 1073 K for up to 1963 h. Contamination by carbon (C) and nitrogen (N) from the Li on the order of thousands of wppm were observe
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ecaa8ef706ea516b95b4c3923ca2b1c6
https://doi.org/10.1016/j.fusengdes.2005.09.029
https://doi.org/10.1016/j.fusengdes.2005.09.029
Autor:
Martin L. Grossbeck
Publikováno v:
Journal of Nuclear Materials. :615-619
Biaxial creep specimens of V–4Cr–4Ti were exposed to liquid lithium at 665 and 765 °C to complement similar tests in a vacuum environment. Although the Li tests are at an early stage, results are consistent with those of the vacuum tests. At 765
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::8e015540c4c99c4c037f2dc863c414d9
https://doi.org/10.1016/s0022-3115(02)01017-6
https://doi.org/10.1016/s0022-3115(02)01017-6
Publikováno v:
Journal of Nuclear Materials. :1595-1599
Gas-tungsten-arc (GTA) weld joints were made from V–4Cr–4Ti alloys in which oxygen levels at the weld metal ranged from 73 to 355 wppm. Both the weld metal and the base metal of the joints showed hardening after the welding. In this study, the in
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::64c2b9753c20c0dfdb1a7ca2e15d3940
https://doi.org/10.1016/s0022-3115(02)01170-4
https://doi.org/10.1016/s0022-3115(02)01170-4
Publikováno v:
Journal of Nuclear Materials. :1590-1594
Gas tungsten arc welding in vanadium alloys is controlled by interstitial impurities. Techniques have been developed to weld V–4Cr–4Ti in a high-purity argon atmosphere resulting in a DBTT of −20 °C. The atmosphere was controlled by a Zr–Al
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::24b2eda25551e699e4b05beb5f96af83
https://doi.org/10.1016/s0022-3115(02)00968-6
https://doi.org/10.1016/s0022-3115(02)00968-6
Publikováno v:
Journal of Nuclear Materials. 299:157-164
In this work, brazing V–5Ti–5Cr to 304 stainless steel (SS 304) using Au–18Ni alloy as filler material was conducted under high vacuum condition. Sessile drop technique was used to determine the wettability of filler alloy to the stainless stee
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::e15e40ccfaf71bc01798f75ce0456504
https://doi.org/10.1016/s0022-3115(01)00677-8
https://doi.org/10.1016/s0022-3115(01)00677-8