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International Association for Structural Mechanics in Reactor Technology (IASMiRT)
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Now showing items 21-40 of 52

Finite Element Analysis for Creep Damage of Coolant Piping in Light Water Reactor due to Local Heating under Severe Accident Condition

Seiya Hagihara; Noriyuki Miyazaki; Jun Sugimoto (IASMiRT, 1999-08-15)
FOREVER Experimental Program on Reactor Pressure Vessel Creep Behavior and Core Debris Retention

B.R. Sehgal; R.R. Nourgaliev; T.N. Dinh; A. Karbojian (IASMiRT, 1999-08-15)
General description of the great Devnya's accicent of a gas explosion

V.A. Dzhupanov (IASMiRT, 1997-08-17)
Large scale combustion tests in the RUT facility: Experimental study, numerical simulations and analysis on turbulent deflagration and DDT

S.B. Dorofeev; V.P. Sidorov; W. Breitung; A. Kotchourko (IASMiRT, 1997-08-17)
LMR large accident analysis method

Y. Cariou; J.P. Purus; C. Avallet (IASMiRT, 1997-08-17)
LMR's whole core accident. Validation of the PLEXUS code by comparison with MARS test

Y. Cariou; M. Lepareux; H. Noe (IASMiRT, 1997-08-17)
Lower head temperature fields for corvis experiments with oxidic melt

J.H. Fokkens; G. Duijvestijn; H. Braam (IASMiRT, 1997-08-17)
Mechanical behavior simulation of TMI-2 lower head using LOHEY module

L.A. Bolshov; R.V. Arutyunan; V. Strizov; N. Yamshchikov; A. Boldyrev (IASMiRT, 1997-08-17)
Numerical simulation of a BWR vessel lower head with penetration subjected to a postulated core damage accident

D. Azodi; P. Gruner (IASMiRT, 1997-08-17)
Physical analysis of combustion tests in the RUT facility and simulation of the detonations

P. Armand; J. Vendel; P. Galon (IASMiRT, 1997-08-17)
Reactor Pressure Vessel Head Louded by a Corium Slug Results of Model Experiments BERDA I

R. Krieg; B. Goller; G. Hailfinger; G. Messemer; G. Vorberg (IASMiRT, 1999-08-15)
Rupther - An original experimental approach for creep failure study of RPV steel

C. Sainte Catherine; Ph. Mongabure; V. Cotoni; L. Nicolas; J. Devos; Ph. Dupas; S. Bhandari (IASMiRT, 1997-08-17)
Scaled experiments for a simple deformable structure under liquid slug impact

T. Stach; T. Malmberg; R. Krieg (IASMiRT, 1997-08-17)
Screening calculations on the vessel lower head behaviour due to an in-vessel steam explosion

M.F. Robbe; M. Lepareux; N. Vivien; G. Cenerino (IASMiRT, 1997-08-17)
Sensitivity Studies on Molten Core Concrete Interaction Using MELCOR Code

Seong Wan Hong; Dong Ha Kim; Jong Kyun Park; Song Won Cho; Soo Yong Park (IASMiRT, 1999-08-15)
Severe Accident Research Activities in Korea: In-Vessel Retention of Molten Core Material

K.Y. Suh; S.H. Chang; H.D.Kim; S.J. Oh; J.L. Lee (IASMiRT, 1999-08-15)
Stability evaluation of PWR containment steel liner for given flaws by use of 2D and 3D FEM computation

O. David; J.M. Humbert; C. Duval (IASMiRT, 1997-08-17)
Status of investigations on hydrogen management measures in German light water reactors

Th. Fröhmel; J. Rohde (IASMiRT, 1997-08-17)
Steam explosion load capacity VVER-1000 NPP reactor cavity

P. Varpasuo (IASMiRT, 1997-08-17)
Study for Therrnal and Structural Behavior of Reactor Pressure Vessel under External Reactor Vessel Cooling

Jong-Sung Kim; Tae-Eun Jin (IASMiRT, 1999-08-15)

Now showing items 21-40 of 52