Citation: | Liu Yang, Lu Zhiwei, Ge Hongen, Wu Lixiang, Xue Jiaxiang, Liao Yehong. Study on Internal Pressure Burst, Creep and Fatigue Properties of ODS-FeCrAl Alloy Tube[J]. Nuclear Power Engineering, 2024, 45(S1): 145-151. doi: 10.13832/j.jnpe.2024.S1.0145 |
[1] |
VISWANATHAN U K, SAH D N, RATH B N, et al. Measurement of fission gas release, internal pressure and cladding creep rate in the fuel pins of PHWR bundle of normal discharge burnup[J]. Journal of Nuclear Materials, 2009, 392(3): 545-551. doi: 10.1016/j.jnucmat.2009.04.021
|
[2] |
YADAV A K, MAJUMDAR P, KUMAR R, et al. Experimental simulation of asymmetric heat up of coolant channel under small break LOCA condition for PHWR[J]. Nuclear Engineering and Design, 2013, 255: 138-145. doi: 10.1016/j.nucengdes.2012.11.002
|
[3] |
SAWARN T K, BANERJEE S, PANDIT K M, et al. Study of clad ballooning and rupture behavior of fuel pins of Indian PHWR under simulated LOCA condition[J]. Nuclear Engineering and Design, 2014, 280: 501-510. doi: 10.1016/j.nucengdes.2014.10.011
|
[4] |
KHAN M K, PATHAK M, DEO A K, et al. Burst criterion for zircaloy-4 fuel cladding in an inert environment[J]. Nuclear Engineering and Design, 2013, 265: 886-894. doi: 10.1016/j.nucengdes.2013.08.071
|
[5] |
LIMON R, LEHMANN S. A creep rupture criterion for Zircaloy-4 fuel cladding under internal pressure[J]. Journal of Nuclear Materials, 2004, 335(3): 322-334. doi: 10.1016/j.jnucmat.2004.07.039
|
[6] |
O’DONNELL W J, LANGER B F. Fatigue design basis for Zircaloy components[J]. Nuclear Science and Engineering, 1964, 20(1): 1-12. doi: 10.13182/NSE64-A19269
|
[7] |
YAMAMOTO Y, PINT B A, TERRANI K A, et al. Development and property evaluation of nuclear grade wrought FeCrAl fuel cladding for light water reactors[J]. Journal of Nuclear Materials, 2015, 467: 703-716. doi: 10.1016/j.jnucmat.2015.10.019
|
[8] |
GAMBLE K A, BARANI T, PIZZOCRI D, et al. An investigation of FeCrAl cladding behavior under normal operating and loss of coolant conditions[J]. Journal of Nuclear Materials, 2017, 491: 55-66. doi: 10.1016/j.jnucmat.2017.04.039
|
[9] |
YANO Y, TANNO T, OKA H, et al. Ultra-high temperature tensile properties of ODS steel claddings under severe accident conditions[J]. Journal of Nuclear Materials, 2017, 487: 229-237. doi: 10.1016/j.jnucmat.2017.02.021
|
[10] |
WU S J, LI J, LI C J, et al. Preliminary study on the fabrication of 14Cr-ODS FeCrAl alloy by powder forging[J]. Journal of Materials Science & Technology, 2021, 83: 49-57.
|
[11] |
LI J, WU S J, MA P, et al. Microstructure evolution and mechanical properties of ODS FeCrAl alloys fabricated by an internal oxidation process[J]. Materials Science and Engineering: A, 2019, 757: 42-51. doi: 10.1016/j.msea.2019.04.088
|
[12] |
DRYEPONDT S, UNOCIC K A, HOELZER D T, et al. Development of low-Cr ODS FeCrAl alloys for accident-tolerant fuel cladding[J]. Journal of Nuclear Materials, 2018, 501: 59-71. doi: 10.1016/j.jnucmat.2017.12.035
|
[13] |
常宇宏. 氧化物弥散强化铁素体合金制备及性能研究[D]. 北京: 北京科技大学,2014.
|
[14] |
CHO H S, OHKUBO H, IWATA N, et al. Improvement of compatibility of advanced ferritic steels with super critical pressurized water toward a higher thermally efficient water-cooled blanket system[J]. Fusion Engineering and Design, 2006, 81(8-14): 1071-1076. doi: 10.1016/j.fusengdes.2005.09.056
|
[15] |
CASTRO V D, JENKINS M. Oxide nanoparticle dispersion in an ODS/Fe12Cr model alloy[J]. Microscopy and Microanalysis, 2008, 14(S2): 646-647. doi: 10.1017/S1431927608083335
|
[16] |
LIU T, WANG C X, SHEN H L, et al. The effects of Cr and Al concentrations on the oxidation behavior of oxide dispersion strengthened ferritic alloys[J]. Corrosion Science, 2013, 76: 310-316. doi: 10.1016/j.corsci.2013.07.004
|
[17] |
KLIMENKOV M. Quantitative measurement of argon inside of nano-sized bubbles in ODS steels[J]. Journal of Nuclear Materials, 2011, 411(1-3): 160-162. doi: 10.1016/j.jnucmat.2011.01.104
|
[18] |
MORLEY N B, ABDOU M A, ANDERSON M, et al. Overview of fusion nuclear technology in the US[J]. Fusion Engineering and Design, 2006, 81(1-7): 33-43. doi: 10.1016/j.fusengdes.2005.06.359
|
[19] |
OKSIUTA Z, BALUC N. Optimization of the chemical composition and manufacturing route for ODS RAF steels for fusion reactor application[J]. Nuclear Fusion, 2009, 49(5): 055003. doi: 10.1088/0029-5515/49/5/055003
|
[20] |
GAO R, ZHANG T, WANG X P, et al. Effect of zirconium addition on the microstructure and mechanical properties of ODS ferritic steels containing aluminum[J]. Journal of Nuclear Materials, 2014, 444(1-3): 462-468. doi: 10.1016/j.jnucmat.2013.10.038
|
[21] |
温敦古,谭军,陈刘涛,等. 核用锆合金包壳管内压爆破试验及性能研究[J]. 材料研究与应用,2016, 10(1): 48-52. doi: 10.3969/j.issn.1673-9981.2016.01.010
|