References
- Alimov VK, Ertl K, Roth J. Deuterium retention and lattice damage in tungsten irradiated with Dions. J Nucl Mater. 2001;s 290–293(2001):389–393.
- Causey RA, Doerner R, Fraser H, et al. Defects in tungsten responsible for molecular hydrogen isotope retention after exposure to low energy plasmas. J Nucl Mater. 2009;390–391:717–720.
- Hatano Y, Shimada M, Alimov VK, et al. Trapping of hydrogen isotopes in radiation defects formed in tungsten by neutron and ion irradiations. J Nucl Mater. 2013;438:S114–S119.
- Markelj S, Ogorodnikova OV, Pelicon P, et al. In situ nuclear reaction analysis of D retention in undamaged and self-damaged tungsten under atomic D exposure. Phys Scripta. 2014;T159:014047.
- Zhang J, Jiang W, Zhu Z, et al. Thermal annealing behavior of hydrogen and surface topography of H2 ion implanted tungsten. J Nucl Sci Technol. 2018;55(7):703–708.
- Sakasegawa H, Tanigawa H, Hamaguchi D. Application of various observational techniques to the characterization of MX in F82H. J Nucl Sci Technol. 2018;55(10):1163–1171.
- Zhang T, Schut H, Li Z, et al. Positron annihilation and nano indentation analysis of irradiation effects on the microstructure and hardening of A508 3 steels used in Chinese HTGR. J Nucl Sci Technol. 2018;55(4):418–423.
- Chen H, Yan M, Long C, et al. Effect of iodine partial pressure on the iodine stress corrosion cracking behaviors of Zr–sn–nb alloy using the ring tensile test. J Nucl Sci Technol. 2018;55(10):496–502.
- Kondo T, Ohishi Y, Muta H, et al. Thermal conductivity and electrical resistivity of liquid Ag In alloy. J Nucl Sci Technol. 2018;55(5):568–574.
- Cho SH, Kim DY, Kwon SC, et al. High temperature corrosion characteristics of yttria stabilized zirconia material in molten salts of LiCl Li2O and LiCl Li2O Li. J Nucl Sci Technol. 2018;55(1):97–103.
- Gao X, Sasaki R, Zheng L, et al. Interaction between B4C 304 stainless steel and Zircaloy 4 in H2O H2 atmosphere at 1473 K. J Nucl Sci Technol. 2018;55(4):400–409.
- Sasaki S, Maeda K, Furuya H. Irradiation performance of sodium-bonded control rod for the fast breeder reactor. J Nucl Sci Technol. 2018;55(3):276–282.
- Sumita T, Urata K, Morita Y, et al. Dissolution behavior of core structure materials by molten corium in boiling water reactor plants during severe accidents. J Nucl Sci Technol. 2018;55(3):267–275.
- Robert NW. Resistance of solid surfaces. Ind Eng Chem. 1936;28:988–994.
- Ishii H, Kurosaki K, Murakami Y, et al. Wettability of liquid caesium iodine and boron oxide on yttria-stabilized zirconia. J Nucl Sci Technol. 2018;55(8):838–842.
- Zinkle SJ, Terrani KA, Gehin JC, et al. Accident tolerant fuels for LWRs: A perspective. J Nucl Mater. 2014;448:374–379.
- Duan ZG, Yang HL, Satoh Y, et al. Current status of materials development of nuclear fuel cladding tubes for light water reactors. Nucl Eng Des. 2017;316:131–150.
- Yueh Y, Terrani KA. Silicon carbide composite for light water reactor fuel assembly applications. J Nucl Mater. 2014;448:380–388.
- Maeda Y, Fukami K, Kondo S, et al. Irradiation-induced point defects enhance the electrochemical activity of 3C-SiC: an origin of SiC corrosion. Electrochem Commn. 2018;91:15–18.
- Shibata H, Ukai S, Oono NH, et al. Development of accident tolerant FeCrAl-ODS steels utilizing Ce-oxide particles dispersion. J Nucl Mater. 2018;502:228–235.
- Toyota K, Hashimoto N. Microstructural Evolution in Fe-Cr-Al Alloys under Irradiation. J Jap Inst Metals. 2018;82:147–152.