共 50 条
- [1] CANDU REACTOR SAFETY SYSTEMS TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1976, 23 (JUN18): : 63 - 64
- [4] CANDU OPERATIONAL EXPERIENCES RELATED TO REACTOR SAFETY ANALYSIS TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1980, 35 (NOV): : 152 - 154
- [8] THE CANDU APPROACH TO DIGITAL SAFETY SYSTEMS NUCLEAR ENGINEERING INTERNATIONAL, 1991, 36 (446): : 35 - 37
- [10] In reactor measurements of CANDU type fuel rods thermal behaviour ANNUAL MEETING ON NUCLEAR TECHNOLOGY '99, PROCEEDINGS, 1998, : 405 - 408