Posters

D01 - Properties and Modelling of Nuclear Concrete

Investigation of Viscoelastic Properties of Irradiated Cement Paste Using Statistical Creep Nanoindentation

P. Patil¹, C. Jones¹, B. Peterman¹, A. Cebula¹

1: Kansas State University, Manhattan, Kansas State, USA

D06 - Fatigue and Thermal Design

Design Curves for the Reactor Enclosure System of the Molten Chloride Reactor Experiment

G. Markham¹, R. Rajasekaran¹, R. Christensen¹

1: TerraPower, LLC, Bellevue, USA

Division 01 - Mechanics of Materials

Annealing Studies on FeCrAl Fuel Cladding

J. Eapen¹, H. Abouelella¹, K. Murty¹

1: North Carolina State University, Raleigh, USA

Reconsideration of Wall-Base Mat Shear for PCCVs to Estimate Limit States

S. Mhamankar¹, C. Jones¹, R. Peterman¹

1: Department of Civil Engineering, Kansas State University, Manhattan, USA

Creep Response in Ultra High Performance Concrete

R. Rogowski¹, C. Jones¹, R. Peterman¹

1: Kansas State University, Manhattan, Kansas, USA

Division 04 - External, Internal Hazards and Load Characterisation

Study on the Strong Ground Motion Prediction Method by HERP, Japan, to 2010 Mw8.8 Maule Earthquake, Chile

S. Dorjpalam¹, Y. Okada¹, K. Irie¹, H. Torita¹

1: Ohsaki Research Institute, Inc., Tokyo, Japan

Impact Testing in VTT

A. Fedoroff¹, K. Calonius¹, A. Vepsä¹, A. Saarenheimo¹

1: VTT Technical Research Centre of Finland Ltd, Espoo, Finland

Division 05 - Modelling, Testing & Response Analysis of Structures, Systems and Components

Analysis of dynamic characteristics of reactor vessel including adjacent equipment

E.-h. Lee¹, C. Ra¹, S.-J. Lee², Y. Choi³, N.-C. Park¹

1: Yonsei university, Seoul, South Korea
2: SEMES Co., Ltd., Seoul, South Korea
3: Korea Institute of Nuclear Safety, Seoul, South Korea

Effect of Shell Element Mesh Size on Finite Element Results

T. Naumov¹, J. Hadfield², M. Tan²

1: Mott MacDonald, Sofia, Bulgaria
2: Mott MacDonald, Altrincham, United Kingdom

A study on Methodologies of time-history analysis of the nuclear power plant piping for the multi-support excitation

C. Ra¹, E.-h. Lee¹, H. Roh¹, N.-c. Park¹

1: Yonsei. Univ., Seoul, South Korea

Division 07 - Safety, Reliability, Risk and Safety Margins

Response Reduction Effect of Seismic Isolation System Considering Uncertainty Parameters for Seismic Margin Assessment

H. Yamano¹, S. Okamura²

1: Japan Atomic Energy Agency, Oarai, Japan
2: Toyama Prefectural University, Toyama, Japan