16th International Conference on 
Structural Mechanics in Reactor Technology

 

DIVISION W: DECOMMISSIONING OF NUCLEAR FACILITIES AND WASTE MANAGEMENT

 

Spent Nuclear Fuel Storage - Feasibility Considerations

1055 Numerical Analysis of Long-Term Thermomechanical Behavior of Repository Structures
Pudewills, Alexandra
1504 Technical Issues Related to Siting Criteria and Seismic Design of ISFSI using DCSS
Tripathi, Bhasker (Bob) P.; Shah, Mahendra J.
1601 Influence of ISFSI Design Parameters on the Seismic Response of Dry Storage Casks
Bjorkman, Gordon S.; Moore, Donald P.; Nolin, Jeffrey J.; Thompson, Victor J.
1612 Impact Resistance of a Concrete Bed for a Spent Nuclear Fuel Cask Repository
Aquaro, Donato; Castrataro, Piero; Forasassi, Giuseppe
1959 The Best Utilization of Nuclear Breeze
Kianoosh, Hassan; Faghih Motlagh, Hassan; Keypour, Hafez

Dry Cask Storage Systems Behavior and Testing

1142 Drop Analysis for Transport Cask of Spent Fuel Rods for Tianwan Nuclear Power Plant
Varpasuo, Pentti
1309 Behavior of Spent Fuel and Safety-Related Components in Dry Cask Storage Systems
Kenneally, Roger M.; Kessler, John H.
1369 Seismic Analysis and Evaluation of Spent Fuel Dry Cask Storage Systems
Luk, Vincent K.; Smith, Jeffery A.; Shaukat, S. Khalid; Kenneally, Roger M.; Dameron, Robert A.; Rashid, Yusef R.; Sobash, V.P.
1643 Effects of Physical Demands on Radwaste Canister
Riera, Francisco; Martí, Joaquín; Mayoral, Felix
1787 Containment and Analysis Capability Insights Gained from Drop Testing Representative Spent Nuclear Fuel Containers
Morton, Dana Keith; Snow, Spencer D.; Rahl, Tom E.; Ware, Arthur G.

Material Applications and Decontamination

1081 Structural Analysis of the Container-Shaped Package of Radioactive Waste
Chung, Sung-Hwan; Lee, Heung-Young; Lee, Ho-Chul; Lee, Young-Shin
1225 Encapsulation Plant for Nuclear Fuel Disposal
Kukkola, Tapani; Raiko, Heikki J.; Salo, Jukka-Pekka
1285 A New Concrete Shielding Material for Waste Management
Warnke, Ernst Peter; Wienert, Reiner; Kramm, Karl-Heinz; Bounin, Dieter
1838 Pilot-scale Test for Vitrification of Simulated Ion Exchange Resin
Choi, Kwansik; Kim, Cheon-Woo; Park, Jong Kil; Park, Byoung Chul; Yang, Kyoung-Hwa; Shin, Sang-Woon; Brunelot, Pierre; Flament, Thierry
1962 Application of Electrical Fields in the Study of Concretes with Respect to the Transport of Several Ionic Species Present in Radioactive Wastes: Characterisation and Decontamination
Castellote, Marta; Andrade, Carmen; Alonso, C.

1/4 Scale Prestressed Concrete Containment Vessel Model Test

1158 Numerical Study on Ultimate Behavior of 1/4 PCCV Model Subjected to Internal Pressure
Yonezawa, Kenji; Imoto, Katsuyoshi; Kato, Asao; Ozaki, Masahiko; Kiyohara, Kazuhiko; Murazumi, Yasuyuki; Sato, Kunihiko
1161 Pretest Analysis of a 1/4 Scale Prestressed Concrete Containment Vessel Model
Mitsugi, Shiro; Kashiwase, Takako; Nagasaka, Hideo
1271 Pretest Analysis of A 1:4- Scale Prestressed Concrete Containment Vessel Model
Dameron, Robert A.; Rashid, Yusef R.; Luk, Vincent K.; Hessheimer, Michael F.
1283 Preliminary Results of a 1:4- Scale Prestressed Concrete Containment Vessel Model Test
Hessheimer, Michael F.; Klamerus, Eric W.; Rightley, Gina S.; Dameron, Robert A.; Shibata, Satiru.; Mitsugi, Shiro; Costello, James F.
1305 Pretest Round Robin Analysis of 1:4- Scale Prestressed Concrete Containment Vessel Model
Hessheimer, Michael F.; Luk, Vincent K.; Klamerus, Eric W.; Shibata, Satiru.; Mitsugi, Shiro; Costello, James F.
1476 Response Simulation of 1/4-Scale Prestressed Concrete Containment Vessel Model
Lee, Nam Ho; Moon, Il Hwan
1529 Analytical Studies of the Actual Scale Steel Containment Vessel Model
Kitajima, Yasumi; Shibata, Satiru

Nuclear Plant Aging and PSA

2076 Probabilistic Fracture Mechanics Based Assessments for Aged Nuclear Structure Components
Yoshimura, Shinobu; Yagawa, Genki; Kanto, Yasuhiro; Shibata, Katsuyuki

 

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