Slide 1WP 5 Safety and Transient Analysis Task 5.6 Containment and source term assessment for the ETDR LEADER Lead-cooled European Advanced DEmonstration Reactor WP 5 - MEETING…
Appendix B - Aging Management Programs Three Mile Island Nuclear Station Unit 1 Page B-1 License Renewal Application APPENDIX B AGING MANAGEMENT PROGRAMS TABLE OF CONTENTS…
Slide 1 Tracking and Trending of Steam Generator Leak Rate (SGLR) Monitor Backgrounds and Source Checks Anthony T Lonnett FENOC - BVPS Units 1 & 2 PO Box 4 ( Mail Stop…
Slide 1 Phenomena of vapor transport in SGTR analysis Pavel Kudinov and Nam Dinh Division of Nuclear Power Safety Royal Institute of Technology (KTH) Stockholm, Sweden 1.SGTR…
Phenomena of vapor transport in SGTR analysis Pavel Kudinov and Nam Dinh Division of Nuclear Power Safety Royal Institute of Technology (KTH) Stockholm, Sweden SGTR induced…
Some of the Major Considerations in Designing a Ceramic Breeder Blanket for ARIES-CS Presented by A. R. Raffray With contribution from S. Malang and the ARIES team ARIES…
PRESENTATION NAME LEADER Project â WP5 Giacomino Bandini - ENEA/Bologna LEADER 4th WP5 Meeting Karlsruhe, 22 November 2012 Task 5.5: âAnalyses of representative DEC events…
Transactions of the 17th International Conference on Structural Mechanics in Reactor Technology (SMiRT 17) Prague, Czech Republic, August 17 â22, 2003 Paper # D04-5 1 Wear…