H.-G. Willschütz

Assessment of reactor vessel integrity (ARVI)

B.R. Sehgal, Ananda Theerthan, Asis Giri et al. · Nuclear Engineering and Design · 2003 · 73 citations

Engineering, Nuclear Engineering, Nuclear Instrumentation +11

Recursively coupled thermal and mechanical FEM-analysis of lower plenum creep failure experiments

H.-G. Willschütz, E. Altstadt, B.R. Sehgal et al. · Annals of Nuclear Energy · 2005 · 38 citations

Engineering, Computational Engineering, Mechanical Engineering +14

Coupled thermal structural analysis of LWR vessel creep failure experiments

H.-G. Willschütz, E. Altstadt, Bal Raj Sehgal et al. · Nuclear Engineering and Design · 2001 · 34 citations

Engineering, Civil Engineering, Marine Engineering +14

Simulation of creep tests with French or German RPV-steel and investigation of a RPV-support against failure

H.-G. Willschütz, E. Altstadt, B.R. Sehgal et al. · Annals of Nuclear Energy · 2003 · 29 citations

Natural Sciences, Materials Engineering, Materials Science +14

Investigations on in-vessel melt retention by external cooling for a generic VVER-1000 reactor

P. Tusheva, E. Altstadt, H.-G. Willschütz et al. · Annals of Nuclear Energy · 2014 · 22 citations

Engineering, Mechanical Engineering, Nuclear Engineering +14