共 50 条
- [42] EXPERIMENTAL AND MCNP5 BASED EVALUATION OF NEUTRON AND GAMMA FLUX IN THE IRRADIATION PORTS OF THE UNIVERSITY OF UTAH RESEARCH REACTOR NUCLEAR TECHNOLOGY & RADIATION PROTECTION, 2012, 27 (03): : 222 - 228
- [46] ESTIMATION OF DOSES RECEIVED BY OPERATORS IN THE 1958 RB REACTOR ACCIDENT USING THE MCNP5 COMPUTER CODE SIMULATION NUCLEAR TECHNOLOGY & RADIATION PROTECTION, 2012, 27 (03): : 199 - 221
- [47] RADIATION SAFETY EVALUATION OF THE HANARO RESEARCH REACTOR SPENT FUEL DISPOSAL SYSTEM NUCLEAR TECHNOLOGY & RADIATION PROTECTION, 2011, 26 (01): : 50 - 57
- [50] Safety analysis of spent fuel element storage in 10 MW high temperature gas-cooled reactor Qinghua Daxue Xuebao/Journal of Tsinghua University, 2001, 41 (10): : 49 - 51