共 50 条
- [41] CATHARE simulation on coupled neutronics/thermal-hydraulics of molten salt reactor (MSR) Hedongli Gongcheng, 4 (16-19+89):
- [43] A STUDY OF PLUTONIUM RECYCLE IN A GAS-COOLED GRAPHITE-MODERATED REACTOR .3. JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY-TOKYO, 1965, 2 (02): : 57 - +
- [45] Correction to: Assembly-level analysis on temperature coefficient of reactivity in a graphite-moderated fuel salt reactor fueled with low-enriched uranium Nuclear Science and Techniques, 2024, 35
- [47] ANALYSIS OF EXPERIMENTAL SPECTRA OF GRAPHITE-MODERATED D-T NEUTRONS TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1981, 39 : 792 - 793
- [48] Xenon Behavior in Molten Salt Reactor Graphite JOURNAL OF NUCLEAR ENGINEERING AND RADIATION SCIENCE, 2020, 6 (04):
- [49] Coupled neutronics and thermal-hydraulics numerical simulations of a Molten Fast Salt Reactor (MFSR) SNA + MC 2013 - JOINT INTERNATIONAL CONFERENCE ON SUPERCOMPUTING IN NUCLEAR APPLICATIONS + MONTE CARLO, 2014,