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International Association for Structural Mechanics in Reactor Technology (IASMiRT)
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Showing items 1-12 of 12

An Assessment of Selected Safety Issues of the New Russian VVER-64O

R. Kirmse; J. Rohde; H. Schaefer (IASMiRT, 1999-08-15)
Application of the Stress-Strength Interference Model to the Design of a Thermal-Hydraulic Passive System for Advanced Reactors

L. Burgazzi (IASMiRT, 2007-08-12)
Defense-in-Depth and Diversity Evaluation to Cope with Non-LOCA with Concurrent Common Mode Failure in Digital Plant Protection System for KNGR

Cheol-Shin Lee; Gyu-Cheon Lee; Chul-Jin Choi; Jong-Tae Seo (IASMiRT, 1999-08-15)
Development Status on the Safety and Regulatory Requirements and Guidance for the Korea Next Generation Reactors

J-H. Lee; W.S. Kim; Y.G. Yune; J-S. Lee; H.S. Chang (IASMiRT, 1999-08-15)
Development of the Three Dimensional Fatigue Analysis Procedure for Major Components of the New Advanced Power Reactor

T. Kim; C. Moon; B. Kim (IASMiRT, 2007-08-12)
Evaluation of Design Transients for thc Extended Design Life of KNGR

Dong-Su Kim; Jong-Joo Sohn; Jong-Ho Choi; Jong-Tae Seo; Sang-Keun Lee (IASMiRT, 1999-08-15)
MARS-GCR Analysis for a New Design of Reactor Cavity Cooling System

Y.J. Cho; H. Kyu Cho; G.C. Park (IASMiRT, 2007-08-12)
Mechanical Structure Design Features of the KALIMER-600 Sodium-Cooled Fast Reactor

J.H. Lee; C.G. Park.; J.-B. Kim; G.H. Koo (IASMiRT, 2007-08-12)
Optimisation of Support Design of Tubes in a Sodium to Air Exchange from Thermal, Vibration and Seismic Loading Considerations

R. Srinivasan; A. Biswas; S. Jaladeen; P. Chellapandi; S.C. Chetal; B. Raj (IASMiRT, 2007-08-12)
Recent Achievement within the French-German Safety Approach for Future PWRs

W. Frisch; G. Gros; F. Rollinger; M. Simon (IASMiRT, 1999-08-15)
Sensitivity of Irradiation-induced Stress in Nuclear Graphite to Material Data

H. Wang; L. Sun; Z. Zhan (IASMiRT, 2007-08-12)
The OBE Elimination in Piping Design

Hee-Cheol Cho; In-Yeung Kim; Soon-Chul Yun; Koo-Woun Park (IASMiRT, 1999-08-15)

Showing items 1-12 of 12