共 11 条
- [1] WHITE J T, NELSON A T, DUNWOODY J T, Et al., Thermophysical properties of U3Si2 to 1773 K, Journal of Nuclear Materials, 464, pp. 275-280, (2015)
- [2] 54, pp. 240-245, (2020)
- [3] ZHOU W Z, LIU R, REVANKAR S T., Fabrication methods and thermal hydraulics analysis of enhanced thermal conductivity UO2-BeO fuel in light water reactors, Annals of Nuclear Energy, 81, pp. 240-248, (2015)
- [4] YEO S, MCKENNA E, BANEY R, Et al., Enhanced thermal conductivity of uranium dioxide-silicon carbide composite fuel pellets prepared by Spark Plasma Sintering (SPS), Journal of Nuclear Materials, 433, 1-3, pp. 66-73, (2013)
- [5] 48, 11, pp. 106-113, (2019)
- [6] GAMBLE K A, BARANI T, PIZZOCRI D, Et al., An investigation of FeCrAl cladding behavior under normal operating and loss of coolant conditions, Journal of Nuclear Materials, 491, pp. 55-66, (2017)
- [7] SINGH G, TERRANI K, KATOH Y., Thermomechanical assessment of full SiC/SiC composite cladding for LWR applications with sensitivity analysis, Journal of Nuclear Materials, 499, pp. 126-143, (2018)
- [8] DUAN Z G, YANG H L, SATOH Y, Et al., Current status of materials development of nuclear fuel cladding tubes for light water reactors, Nuclear Engineering and Design, 316, pp. 131-150, (2017)
- [9] 3, (2018)
- [10] 4, (2019)