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(2024) Journal of Nuclear Materials Vol. 598. Elsevier BV

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Reference TypeJournal (volume)
JournalJournal of Nuclear MaterialsISSN0022-3115
Year2024Volume<   598   >
PublisherElsevier BV
Mindat Ref. ID17387593Long-form Identifiermindat:1:5:17387593:5
GUID0
Full Reference(2024) Journal of Nuclear Materials Vol. 598. Elsevier BV
Plain Text(2024) Journal of Nuclear Materials Vol. 598. Elsevier BV
InElsevier BV (1959 - ) Journal of Nuclear Materials

Contains

Yu, Jie, Zhao, Fei, Xu, Fahong, Xiong, Suiping, Yang, Ming, Huang, Wensen (2024) Effect of pre-precipitation thermomechanical treatment on precipitation behavior of CLAM steel. Journal of Nuclear Materials, 598. 155119 doi:10.1016/j.jnucmat.2024.155119
Cui, Dewang, Ding, Yifan, Li, Yipeng, Pei, Kefei, Cao, Ziqi, Cao, Ming, Ran, Guang (2024) Dynamic response of He bubbles in Fe9Cr1.5W0.4Si F/M steel under in-situ stepwise nanocompression. Journal of Nuclear Materials, 598. 155131 doi:10.1016/j.jnucmat.2024.155131
Wang, Xutong, Li, Jiuxiao, Yu, Yixiao, Shi, Huigang, Zhao, Zhiwei, Zeng, Qifeng, Liu, Qingdong (2024) From microstructural changes to electrochemical behavior: decoding the corrosion mechanism in Zr-Sn-Nb-Fe-Cr-Mo-O-V alloys. Journal of Nuclear Materials, 598. 155137 doi:10.1016/j.jnucmat.2024.155137
Parsons, Caitlyn B., Simon, Pierre-Clément A., Wirth, Brian D. (2024) Impact of temperature variations on BISON predictions of Ag release in AGR-1 and AGR-2 experiments. Journal of Nuclear Materials, 598. 155139 doi:10.1016/j.jnucmat.2024.155139
Malo, M., Peñalva, I., Roldån, M., Urrestizala, M., Azkurreta, J., Garcinuño, B., Rapisarda, D. (2024) Hydrogen isotope transport parameters in materials for tritium extraction systems. Focus on the low pressure. Journal of Nuclear Materials, 598. 155142 doi:10.1016/j.jnucmat.2024.155142
Evans, Jordan A., Sweet, Ryan T., Medvedev, Pavel G., Wagner, Adrian R., Parisi, Carlo, Lange, Travis L., Perez, Emmanuel, Rice, Francine, Jue, Jan-Fong, Woolstenhulme, Eric, Keiser, Dennis D., Arafat, Yasir (2024) Uranium-zirconium hydride nuclear fuel performance in the NaK-cooled MARVEL microreactor. Journal of Nuclear Materials, 598. 155145 doi:10.1016/j.jnucmat.2024.155145
Cao, Xicheng, Lv, Junnan, Dong, Yingxuan, Hou, Junling, Li, Qun (2024) The pore aggregation characterized by spatial statistics methods and its effect on the damage behavior based on the configurational forces of the M-integral in MOX fuel. Journal of Nuclear Materials, 598. 155146 doi:10.1016/j.jnucmat.2024.155146
Sun, Jiaxing, Sun, Mingwei, Guo, Cuiping, Li, Changrong, Du, Zhenmin (2024) Experimental determination and thermodynamic optimization of the Nb–V–Zr system. Journal of Nuclear Materials, 598. 155160 doi:10.1016/j.jnucmat.2024.155160
Wu, Mengjie, Huang, Jiyong, Cao, Ziqi, Ding, Yifan, Zhong, Qinghong, Zhao, Yanli, Ran, Guang (2024) Effect of hydrogen, helium and dose rate on the evolution of dislocation loop in pure iron during in-situ ion irradiation. Journal of Nuclear Materials, 598. 155161 doi:10.1016/j.jnucmat.2024.155161
MartĂ­nez-Torrents, Albert, Purroy, Daniel Serrano, Kokinda, Jakub, PĂ©rez, Luis Iglesias, Clarens, Frederic, GimĂ©nez, Javier, de Pablo, Joan (2024) Release of Cs, Sr and Rb from two high–burnup spent nuclear fuels: Effect of the dishing and the internal grain boundaries. Journal of Nuclear Materials, 598. 155162 doi:10.1016/j.jnucmat.2024.155162
Porto, G., Bouchet, J., Bathellier, D., Bodin, J., Canducci, M., Tranchida, J., Fossati, P., Martin, P., Bourasseau, E. (2024) Thermodynamic and thermoelastic properties of hypostoichiometric MOX fuels with molecular dynamics simulations. Journal of Nuclear Materials, 598. 155163 doi:10.1016/j.jnucmat.2024.155163
Alam, M.E., Yamamoto, T., Odette, G.R. (2024) Crack self-healing by high-temperature annealing of a 90W7Ni3Fe tungsten heavy alloy. Journal of Nuclear Materials, 598. 155164 doi:10.1016/j.jnucmat.2024.155164
Park, Young Ah, Park, Yi-Hyun, Ahn, Mu-Young, Yoon, Young Soo (2024) Corrigendum to “Fabrication and characteristics of Li2TiO3 pebbles manufactured by using powder injection molding (PIM) process” [JNM 597 (2024) 155140]. Journal of Nuclear Materials, 598. 155165 doi:10.1016/j.jnucmat.2024.155165
Ding, Yifan, Wu, Mengjie, Li, Yipeng, Sun, Yongduo, Zhao, Yanli, Ran, Guang (2024) Quantitative in-situ investigation of dislocation loop motion in Fe9Cr1.5W ferritic/martensitic steel under the coupling effects of constant stress and irradiation. Journal of Nuclear Materials, 598. 155166 doi:10.1016/j.jnucmat.2024.155166
Liu, Xinyi, Cao, Ziqi, Zhong, Qinghong, Ding, Yifan, Li, Yipeng, Cao, Ming, Ran, Guang (2024) In-situ TEM characterization of dislocation loops in tungsten under simultaneous helium and hydrogen irradiation. Journal of Nuclear Materials, 598. 155167 doi:10.1016/j.jnucmat.2024.155167
Yang, L., Wirth, B.D. (2024) First-principles study of helium solution and diffusion in tungsten borides. Journal of Nuclear Materials, 598. 155175 doi:10.1016/j.jnucmat.2024.155175
Gao, Yang, Qiu, Xi, Su, Haozhan, Shi, HuiGang, Zhang, LeFu, Sun, DaYun, Zhou, ZhangJian, Liang, Tian, Guo, XiangLong (2024) Characterization of the oxide film formed on alumina-forming austenitic stainless steel in deaerated, DH, DO, and OT supercritical water. Journal of Nuclear Materials, 598. 155177 doi:10.1016/j.jnucmat.2024.155177
Li, Yongchang, Garner, Frank A., Hu, Zhihan, Shao, Lin (2024) Void swelling in pure iron after sequential self-ion-irradiation at different energies: Effect of injected interstitials and additional damage in regions containing pre-existing voids. Journal of Nuclear Materials, 598. 155178 doi:10.1016/j.jnucmat.2024.155178
Chikhalikar, Atharva S, Qu, Haozheng, Abouelella, Hamdy, Nagothi, Bhavani, Rajendran, Rupesh, Roy, Indranil, Umretiya, Rajnikant, Hoffman, Andrew, Rebak, Raul (2024) Effect of Al content on steam oxidation behavior for ferritic Fe-21Cr-xAl alloys. Journal of Nuclear Materials, 598. 155179 doi:10.1016/j.jnucmat.2024.155179
Zou, D.L., Li, F.F., Liu, F., Zhao, Y.W., Liu, J.Y., Su, B., Liu, K.Z. (2024) Preparation of the gradient nanostructured layer in uranium by surface shot peening treatment. Journal of Nuclear Materials, 598. 155183 doi:10.1016/j.jnucmat.2024.155183
Zsåkai, A., Meléndez, C., Becerril, S., Dézsi, T., Kovåcs, D., Simon, R.S., Korossy-Khayll, A., Oravecz, D.Z., Katona, I., Castellanos, J., Serikov, A., Qiu, Y., Micicché, G., García, M., Ibarra, A. (2024) Evolution of IFMIF-DONES' heart: System overview of the Test Cell. Journal of Nuclear Materials, 598. 155185 doi:10.1016/j.jnucmat.2024.155185
Su, Zhengxiong, Lyu, Sixin, Shi, Tan, Zhang, Ping, Yang, Jinxue, Wang, Jianqiang, Chen, Meiqing, Gao, Rui, Li, Zhiming, Guo, Shaoqiang, Wu, Yingwei, Shen, Huahai, Lu, Chenyang (2024) Fluctuations in misfit volume by interstitial carbon atoms contribute to the unusual dislocation loop evolution in high-entropy alloys under irradiation. Journal of Nuclear Materials, 598. 155186 doi:10.1016/j.jnucmat.2024.155186
Li, Jiaqi, Daghbouj, N., He, Xiaoxun, Chen, Ke, Cao, Xingzhong, Jin, Shuoxue, Li, Jun, Wei, Haiyuan, Zhou, Junjun, Zhang, Tongmin, Xu, Shuai, Ge, Fangfang, Duchoƈ, J., AlMotasem, A.T., Polcar, T., Li, Bingsheng (2024) Helium's impact: Unraveling bubble formation in Fe2AlB2 under extreme conditions of temperature and fluence. Journal of Nuclear Materials, 598. 155187 doi:10.1016/j.jnucmat.2024.155187
Hirooka, Shun, Morimoto, Kyoichi, Matsumoto, Taku, Ogasawara, Masahiro, Kato, Masato, Murakami, Tatsutoshi (2024) Enthalpy measurement on (U1−xPux)O2 (x = 0, 0.18, 0.45, and 1) and analysis of heat capacity. Journal of Nuclear Materials, 598. 155188 doi:10.1016/j.jnucmat.2024.155188
Chen, Jia-Li, Kaltsoyannis, Nikolas (2024) The adsorption of carbon and nitrogen oxides on the PuO2 {110} surface: A DFT + U study. Journal of Nuclear Materials, 598. 155189 doi:10.1016/j.jnucmat.2024.155189
Hasan, ATM Jahid, Beeler, Benjamin (2024) Calculation of grain boundary diffusion coefficients in ÎłU-Mo using atomistic simulations. Journal of Nuclear Materials, 598. 155190 doi:10.1016/j.jnucmat.2024.155190
Deng, Chaoqun, Zhu, Siyang, He, Yanan, Wu, Yingwei, He, Kai, Zhang, Jing, Su, Guanghui (2024) Analysis of gas-cooled micro modular reactor (MMR) fuel. Journal of Nuclear Materials, 598. 155191 doi:10.1016/j.jnucmat.2024.155191
Luo, Fengfeng, Luo, Hongtai, Liu, Qiuxiang, Chen, Liheng, Lin, Wenbin, Long, Yunxiang, Guo, Liping (2024) Dislocation loops and hardening of silicon ion irradiated W and W-3Re alloy at 400 °C and 550 °C. Journal of Nuclear Materials, 598. 155192 doi:10.1016/j.jnucmat.2024.155192
Dasari, Sriswaroop, Kombaiah, Boopathy, Poplawsky, Jonathan D., Bachhav, Mukesh, Edmondson, Philip D., Bei, Hongbin, Kancharla, Rahul Reddy, Zhang, Yanwen (2024) Microstructural evolution in doped high entropy alloys NiCoFeCr-3X (X=Pd/Al/Cu) under irradiation. Journal of Nuclear Materials, 598. 155194 doi:10.1016/j.jnucmat.2024.155194
Imran, Muhammad, Hu, Zhenhua, Zheng, Peichao, Sattar, Harse, Khan, Muhammad Salman, Iqbal, Muzammil, Luo, Guang-Nan, Ding, Fang (2024) Studies of erosion-deposition of plasma-facing materials due to plasma-wall interactions in EAST tokamak. Journal of Nuclear Materials, 598. 155195 doi:10.1016/j.jnucmat.2024.155195
(2024) Editorial Board. Journal of Nuclear Materials, 598. 155215 doi:10.1016/s0022-3115(24)00317-9

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