Irradiation creep of the US Heat 832665 of V–4Cr–4Ti

Li, Meimei; Hoelzer, David T.; Grossbeck, M.L.; Rowcliffe, A.F.; Zinkle, S.J.; Kurtz, Richard J.

doi:10.1016/j.jnucmat.2008.12.220

Cited by 17 publications

(2 citation statements)

References 17 publications

(20 reference statements)

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“…The post-transient irradiation creep was investigated for Data for most of the bulk specimens at less than~1 dpa were obtained in previous studies [5,6]. zirconium alloys [27,28], vanadium alloy (V-4Cr-4Ti) [29], austenitic stainless steels including 316 and 304 [30e32], oxidedispersion-strengthened (ODS) ferritic steels (MA957 and HT9) [33], and ferritic/martensitic steels (F82H and JLF-1) [34,35]. Those irradiation temperatures ranged from~300 to~700 C. The irradiation creep was investigated using a pressurized tube method for all the materials other than SiC.…”

Section: Comparison Of Secondary Irradiation Creep Among Sic and Othementioning

confidence: 99%

Neutron-irradiation creep of silicon carbide materials beyond the initial transient

Koyanagi

Katoh

Ozawa

et al. 2016

Journal of Nuclear Materials

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a b s t r a c tIrradiation creep beyond the transient regime was investigated for various silicon carbide (SiC) materials. The materials examined included polycrystalline or monocrystalline high-purity SiC, nanopowder sintered SiC, highly crystalline and near-stoichiometric SiC fibers (including Hi-Nicalon Type S, Tyranno SA3, isotopically-controlled Sylramic and Sylramic-iBN fibers), and a Tyranno SA3 fiberereinforced SiC matrix composite fabricated through a nano-infiltration transient eutectic phase process. Neutron irradiation experiments for bend stress relaxation tests were conducted at irradiation temperatures ranging from 430 to 1180 C up to 30 dpa with initial bend stresses of up to~1 GPa for the fibers and~300 MPa for the other materials. Initial bend stress in the specimens continued to decrease from 1 to 30 dpa. Analysis revealed that (1) the stress exponent of irradiation creep above 1 dpa is approximately unity, (2) the stress normalized creep rate is~1 Â 10 À7 [dpa À1 MPa À1 ] at 430e750 C for the range of 1e30 dpa for most polycrystalline SiC materials, and (3) the effects on irradiation creep of initial microstructuresdsuch as grain boundary, crystal orientation, and secondary phasesdincrease with increasing irradiation temperature.

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Section: Comparison Of Secondary Irradiation Creep Among Sic and Othementioning

confidence: 99%

Neutron-irradiation creep of silicon carbide materials beyond the initial transient

Koyanagi

Katoh

Ozawa

et al. 2016

Journal of Nuclear Materials

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“…Thermal creep is a strong function of alloy composition and microstructure and in case of FeCrAl alloys it has only received limited attention at high temperatures (≥500°C) [21]. Finally, irradiation creep has received some attention with rough estimates available for bcc metals in the literature [20], [22], [23].…”

Section: Introductionmentioning

confidence: 99%

Input Correlations for Irradiation Creep of FeCrAl and SiC Based on In-Pile Halden Test Results

Terrani

Karlsen

Yamamoto

2016

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Swelling and creep behavior of wrought FeCrAl alloys and CVD-SiC, two candidate accident tolerant fuel cladding materials, are being examined using in-pile tests at the Halden reactor. The outcome of these tests are material property correlations that are inputs into fuel performance analysis tools. The results are discussed and compared with what is available in literature from irradiation experiments in other reactors or out-of-pile tests. Specific recommendation on what correlations should be used for swelling, thermal, and irradiation creep for each material are provided in this document.

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Application of In Situ TEM to Investigate Irradiation Creep in Nanocrystalline Zirconium

Bufford

Barr

Wang

et al. 2019

JOM

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Irradiation creep of the US Heat 832665 of V–4Cr–4Ti

Cited by 17 publications

References 17 publications

Neutron-irradiation creep of silicon carbide materials beyond the initial transient

Neutron-irradiation creep of silicon carbide materials beyond the initial transient

Input Correlations for Irradiation Creep of FeCrAl and SiC Based on In-Pile Halden Test Results

Application of In Situ TEM to Investigate Irradiation Creep in Nanocrystalline Zirconium

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