共 50 条
- [41] Probabilistic method for analysis of fuel rod internal pressure in a nuclear reactor core ANNUAL MEETING ON NUCLEAR TECHNOLOGY '98, PROCEEDINGS, 1998, : 347 - 350
- [43] Neutron analysis for homogeneous nuclear reactor core with a U–Th fuel matrix MRS Advances, 2022, 7 : 1225 - 1229
- [44] Review of JAEA's Monte Carlo codes for nuclear reactor core analysis EPJ NUCLEAR SCIENCES & TECHNOLOGIES, 2025, 11
- [46] Probabilistic method for analysis of fuel rod internal pressure in a nuclear reactor core ANNUAL MEETING ON NUCLEAR TECHNOLOGY '98, PROCEEDINGS, 1998, : 347 - 350
- [47] NUCLEAR ANALYSIS OF GAS CORE REACTOR CONFIGURATIONS FOR MHD POWER-GENERATION TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1973, 16 (JUN): : 243 - 243
- [48] Development of reactor core for nuclear thermal propulsion Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2012, 46 (SUPPL.2): : 889 - 895
- [49] PIEZOELECTRIC MATERIAL FOR USE IN A NUCLEAR REACTOR CORE REVIEW OF PROGRESS IN QUANTITATIVE NONDESTRUCTIVE EVALUATION, VOLS 31A AND 31B, 2012, 1430 : 1633 - 1639