Zobrazeno 1 - 10
of 36
pro vyhledávání: '"J.L. Hollenbeck"'
Publikováno v:
Nuclear Materials and Energy, Vol 19, Iss , Pp 416-432 (2019)
Zircaloy-2 and Zircaloy-4 were neutron irradiated at 358 °C in the high flux isotope reactor (HFIR) to a neutron fluence of 29.6 × 1024 n/m2 (E > 1 MeV) and the resultant irradiation hardening was measured by tensile testing. Irradiation at the rel
Externí odkaz:
https://doaj.org/article/9913587a49f9498e8fb85768812f7ea3
Publikováno v:
Nuclear Materials and Energy, Vol 19, Iss, Pp 416-432 (2019)
Zircaloy-2 and Zircaloy-4 were neutron irradiated at 358 °C in the high flux isotope reactor (HFIR) to a neutron fluence of 29.6 × 1024 n/m2 (E > 1 MeV) and the resultant irradiation hardening was measured by tensile testing. Irradiation at the rel
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::188fe72dad67856b0beca5e5882231c6
https://doi.org/10.1016/j.nme.2019.03.023
https://doi.org/10.1016/j.nme.2019.03.023
Autor:
J.L. Hollenbeck, B.V. Cockeram
Publikováno v:
Journal of Nuclear Materials. 467:9-31
Zircaloy-4 was tested at room-temperature over a range of hydrogen content between 10 and 200 ppm, and stress-states between a triaxiality of −0.23 and 0.9. Triaxiality ( η ) is defined as the ratio of hydrostatic stress to von Mises stress and wa
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f2d6c784ce32505e0aa36219b1239d9d
https://doi.org/10.1016/j.jnucmat.2015.09.012
https://doi.org/10.1016/j.jnucmat.2015.09.012
Publikováno v:
Journal of Nuclear Materials. 461:244-264
The recovery of irradiation damage in wrought Zircaloy-2 and Zircaloy-4 was determined following a series of post-irradiation anneals at temperatures ranging from 343 °C to 510 °C and for time periods ranging from 1-h to 500 h. The materials had be
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::51a76fab1360e415d4366a57855e0adc
https://doi.org/10.1016/j.jnucmat.2015.03.003
https://doi.org/10.1016/j.jnucmat.2015.03.003
Publikováno v:
Journal of Nuclear Materials. 449:69-87
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::3bf0a1817fd611ac1bdc71cef74d2c92
https://doi.org/10.1016/j.jnucmat.2014.03.004
https://doi.org/10.1016/j.jnucmat.2014.03.004
Publikováno v:
Journal of Nuclear Materials. 440:382-413
Commercially available unalloyed molybdenum (Low Carbon Arc Cast (LCAC)), Oxide Dispersion Strengthened (ODS) molybdenum, and TZM molybdenum were subject to fracture toughness testing following neutron irradiation at temperatures of nominally 244 °C
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::1c4ffa0aac0b247885f77874edd10d61
https://doi.org/10.1016/j.jnucmat.2013.05.027
https://doi.org/10.1016/j.jnucmat.2013.05.027
Publikováno v:
Journal of Nuclear Materials. 336:299-313
Hardness and electrical resistivity were measured for LCAC molybdenum following irradiation at 270–1100 °C and neutron fluences of 10.5–64.4 × 10 24 n/m 2 ( E > 0.1 MeV) to provide a basic assessment of the influence of irradiation and post-irr
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::6b390b35c4696babc851eeef62b2b8e2
https://doi.org/10.1016/j.jnucmat.2004.10.119
https://doi.org/10.1016/j.jnucmat.2004.10.119
Publikováno v:
Journal of Nuclear Materials. 324:77-89
Molybdenum alloys are known to be most susceptible to neutron radiation damage at radiation temperatures 0.1 MeV). Irradiation of LCAC molybdenum at nominal temperatures of 935–1100 °C produced only moderate changes in tensile strength, tensile el
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::13201a48923bb01ef0a282887c596e71
https://doi.org/10.1016/j.jnucmat.2003.05.001
https://doi.org/10.1016/j.jnucmat.2003.05.001
Autor:
B.V. Cockeram, J.L. Hollenbeck
Publikováno v:
Surface and Coatings Technology. 157:274-281
Vacuum plasma spray coatings (ZrO 2 +18% TiO 2 +10% Y 2 O 3 , ZrC, Fe 2 TiO 5 , ZrTiO 4 , ZrO 2 +8% Y 2 O 3 +2% HfO 2 , and Al 2 O 3 +TiO 2 ) have been developed to improve the emissivity of material surfaces under consideration for TPV radiator appl
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::e6f1ef2f721938cdc99a577e24d76828
https://doi.org/10.1016/s0257-8972(02)00152-4
https://doi.org/10.1016/s0257-8972(02)00152-4
Autor:
B.V. Cockeram, J.L. Hollenbeck
Publikováno v:
Elevated Temperature Coatings
Coatings or surface modifications are needed to improve the surface emissivity of materials under consideration for TPV radiator applications to a value of 0.8 or higher. Vacuum plasma spray coatings (ZrO{sub 2} + 18% TiO{sub 2} + 10% Y{sub 2}O{sub 3
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c4fa02030f9dac0c7a8e9c4f6120073b
https://doi.org/10.1002/9781118787694.ch25
https://doi.org/10.1002/9781118787694.ch25
