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1. Research on the key design of emergency core cooling scheme for Tsinghua high flux reactor NSTL国家科技图书文献中心
Wang, Zhuang | Lv, Meng... - 《Annals of nuclear energy》 - 2025,211(Feb.) - 1.1~1.21 - 共21页
2. Phase-field simulation of recrystallization and calculation of the effective thermal conductivity of polycrystalline UO2 NSTL国家科技图书文献中心
Jiang Y. | Shen W.... - 《Annals of nuclear energy》 - 2025,211(Feb.) - 1.1~1.10 - 共10页
3. Effects of increasing the gap ratio on performance and pressure pulsations in a mixed-flow reactor coolant pump NSTL国家科技图书文献中心
Liu L. | Gao J.... - 《Annals of nuclear energy》 - 2025,211(Feb.) - 1.1~1.13 - 共13页
Strachota P. | Nyvlt S.... - 《Annals of nuclear energy》 - 2025,211(Feb.) - 1.1~1.17 - 共17页
5. Transient thermal hydraulic analysis of a small passive lead–bismuth eutectic cooled fast reactor NSTL国家科技图书文献中心
Zeng C. | Shen C.... - 《Annals of nuclear energy》 - 2025,210(Jan.) - 1.1~1.15 - 共15页
6. Development of a computational scheme based on the DRAGON5 code for the neutronic study of VVER-type reactor rods and assemblies NSTL国家科技图书文献中心
Richard C. | Francois M.... - 《Annals of nuclear energy》 - 2025,211(Feb.) - 1.1~1.8 - 共8页
7. Adjusting aluminum elastic scattering data from the TALYS nuclear reaction code based upon fast criticalities NSTL国家科技图书文献中心
Pelloni S. | Rochman D. - 《Annals of nuclear energy》 - 2025,211(Feb.) - 1.1~1.11 - 共11页
8. Experimental study on two-phase flow instability in helically coiled tube under rolling motion NSTL国家科技图书文献中心
Wang R. | Ren J.... - 《Annals of nuclear energy》 - 2025,210(Jan.) - 1.1~1.10 - 共10页
Wu H. | Liu S.... - 《Annals of nuclear energy》 - 2025,211(Feb.) - 1.1~1.13 - 共13页
Gremyachkin D.E. | Egorov A.S.... - 《Annals of nuclear energy》 - 2025,211(Feb.) - 1.1~1.11 - 共11页
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