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International Association for Structural Mechanics in Reactor Technology (IASMiRT)
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Showing items 1-13 of 13

Anisotropic Biaxial Creep of Zircaloy Cladding: Effects of Recrystallization and Neutron Irradiation

Sheikh T. Mahmood; William L. Daugherty; K. Linga Murty (IASMiRT, 1989-08-22)
End Plate Design for 37 Element Fuel Bundle

M. Das; A.G. Chhatre; P.N. Prasad (IASMiRT, 1989-08-22)
European Fast Reactor (EFR) Fuel Element Design

A. Pay; E. Francillon; B. Steinmetz; D. Barnes; N. Meda (IASMiRT, 1989-08-22)
Fabrication in Mexico of Fuel Rods for Irradiation in a BWR Reactor

Carlos A. Nocetti; Enrique Velazquez (IASMiRT, 1989-08-22)
Influence of Energy Dissipation on PWR Fuel Assembly Behaviour During Severe Seismic Excitation

J.-D. Kim; U. Borsdorf; H.P. Fuchs; J. Stabel (IASMiRT, 1989-08-22)
Parametric Study of Thermal Feedback and Other Transient Effects, Based on the INTERPIN Code

Niels Kjaer-Pedersen (IASMiRT, 1989-08-22)
PWR Fuel Assembly Grid External Stiffness Determination from Dynamic Crush Tests

J. Rigaudeau; J-C. Leroux; J. Schlosser (IASMiRT, 1989-08-22)
Recent Development of a Fuel Pin Bundle Mechanical Performance Code "ETOILE"-Pin Ovalling Model

Masatoshi Nakagawa; Yasushi Tsuboi (IASMiRT, 1989-08-22)
SATIN: A Computer Model for the Analysis and Prediction of Thermoelastic Vibrations in FBR Gridded Subassemblies

J.-P. Fabry; A. Decauwers (IASMiRT, 1989-08-22)
Status of the European Accident code EAc-2 for LMFBR Safety Analysis with Emphasis on the MOL7C7 Pretest Calculations

G. Van Goethem; K. Lassmann; H.U. Wider (IASMiRT, 1989-08-22)
The Integrity of CANDU Fuel During Load Following

M. Tayal; A.M. Manzer; R. Sejnoha; Y. Kinoshita; A.J. Hains (IASMiRT, 1989-08-22)
Thermoelastic Oscillations of FBR Fuel Pins

André Preumont (IASMiRT, 1989-08-22)
Validation of Models for the Analysis of the Transient Behavior of Metallic Fast Reactor Fuel

J.M. Kramer; T.H. Hughes; E.E. Gruber (IASMiRT, 1989-08-22)

Showing items 1-13 of 13