18th
International Conference on
Structural Mechanics
in Reactor Technology
| 18th
International Conference on |
|
DIVISION
W: DECOMMISSIONING OF NUCLEAR FACILITIES
AND WASTE MANAGEMENT
Decommissioning of Nuclear Facilities and Waste Management
| W01-1 | Finnish
Concept for Spent Nuclear Fuel Disposal Heikki Raiko, Tiina Jalonen, Tapani Kukkola, Jukka-Pekka Salo |
| W01-2 | Shaft
Shock Absorber for a Spent Fuel Canister Tapani Kukkola |
| W01-3 | Collection
and Characterization of Emissions from Metal Cutting in CAORSO Nuclear Power Plant
Decommissioning Franco Giuseppe Cesari, Luigi Andrea Terzi, Angelo Giostri, Cristina Bernini, Enzo Sirito, Massimo Sirito |
| W01-5 | Considerations
on Risk Analysis for Nuclear Spent Fuel Storage Facility of Cernavoda NPP Veronica Andrei, Sorin Ghita, Florin Glodeanu |
Waste Management
| W02-1 | Technology
of Reprocessing High-Level Wastes by Method of Self-Propagating High-Temperature
Synthesis (SPHTS) into Mineral-Like Materials O.A. Yarmolenko, A.A. Romenkov, N.A. Sudareva, Ye.V. Sukhovsky, O.K. Karlina, G.A. Pavlova, A.Yu. Yurchenko |
| W02-2 | Decay
Heat Power and Radiotoxicity of Spent Uranium, Plutonium and Thorium Fuel at Long-Term
Storage Alexander Gerasimov, Boris Bergelson, Tamara Zaritskaya, Gennady Kiselev, Alexander Volovik, Georgy Tikhomirov |
| W02-6 | Application
of Power Reactors for Transmutation of Actinides Boris Bergelson, Alexander Gerasimov, Georgy Tikhomirov |
| W02-7 | Full
System Decontamination with the HP/CORD(R) UV for Decommissioning at German PWR
Stade Ch. Stiepani, H.-O. Bertholdt |
DIVISION WS: WORKSHOPS
Structural
Integrity and Life Time Prediction for Graphite Core Components
Chinese
Nuclear Power
| W301-3 | Low-Medium
Level Radioactive Solid Waste Cask Drop Analysis and Test Chunming Wang |
| W301-4 | A
Design of Compact and Enhanced Heat Exchanger Used in Integrated Nuclear Reactor Minghui Chen, Rizhu Li, Benyuan Li |
| W301-5 | Development
and Application of the Computer Code CAPS (Computer Aided Piping-Analysis System) Shubin Liu, Shangwang Zhang, Yuanzhu Wang, Zhenbang Gong, Shihua Liu |
| W301-8 | Research
on Process Management of Nuclear Power Technology Innovation Hua Yang, Yu Zhou |
| W301-9 | Nuclear
Component Design Ontology Building Based on ASME Codes Shiyi Bao, Yu Zhou, Shuyan He |
| W301-10 | Challenges
and Opportunities for the Development of World Nuclear Power Yinjuan Lu, Zhen Fu, Yu Yang |
| W301-11 | Study
on Concept of Web-Based Reactor Piping Design Data Platform Yu Wang, Yu Zhou, Jianling Dong, Yang Meng |