Quantification of brittle-ductile failure behavior of ferritic reactor pressure vessel steels using the Small-Punch-Test and micromechanical damage modelsLINSE, T; KUNA, M; VIEHRIG, H.-W et al.Materials science & engineering. A, Structural materials : properties, microstructure and processing. 2014, Vol 614, pp 136-147, issn 0921-5093, 12 p.Article

Correlation between volume fraction of radiation-incuced predipitates and toughness of Cr-Mo-V alloyed VVER pressure vessel steelGROSSE, M; BÖHMERT, J; VIEHRIG, H. W et al.Journal of nuclear materials. 1994, Vol 211, Num 2, pp 177-180, issn 0022-3115Article

Acceleration of irradiation hardening of low-copper reactor pressure vessel steel observed by means of SANS and tensile testingBERGNER, F; ULBRICHT, A; VIEHRIG, H.-W et al.Philosophical magazine letters. 2009, Vol 89, Num 12, pp 795-805, issn 0950-0839, 11 p.Article

Correlation between irradiation-induced changes of microstructural parameters and mechanical properties of RPV steelsBÖHMERT, J; VIEHRIG, H.-W; ULBRICHT, A et al.Journal of nuclear materials. 2004, Vol 334, Num 1, pp 71-78, issn 0022-3115, 8 p.Article

Irradiation effects on toughness behaviour and microstructure of VVER-type pressure vessel steelsBÖHMERT, J; VIEHRIG, H.-W; ULBRICHT, A et al.Journal of nuclear materials. 2001, Vol 297, Num 3, pp 251-261, issn 0022-3115Article

Anwendung des instrumentierten Kerbschlagbiegeversuchs zur Ermittlung von Referenztemperaturen nach dem Master-Curve-Konzept = Application of the instrumented impact test for the determination of reference temperatures using the Master curve conceptVIEHRIG, H.-W; BÖHMERT, J; DZUGAN, J et al.Materialwissenschaft und Werkstofftechnik. 2001, Vol 32, Num 6, pp 568-573, issn 0933-5137Article

Measurement of dynamic elastic-plastic fracture toughness parameters using various methodsVIEHRIG, H.-W; POPP, K; RINTAMAA, R et al.International journal of pressure vessels and piping. 1993, Vol 55, Num 2, pp 233-241, issn 0308-0161Conference Paper

The use of acoustic emission to determine characteristic dynamic strength and toughness properties of steelRICHTER, H; BÖHMERT, J; VIEHRIG, H.-W et al.Nuclear engineering and design. 1999, Vol 188, Num 2, pp 241-254, issn 0029-5493Conference Paper

Small-angle neutron scattering investigation of as-irradiated, annealed and reirradiated reactor pressure vessel weld material of decommissioned reactorULBRICHT, A; ALTSTADT, E; BERGNER, F et al.Journal of nuclear materials. 2011, Vol 416, Num 1-2, pp 111-116, issn 0022-3115, 6 p.Conference Paper

Influence of the depth position on the neutron embrittlement of the VVER reactor pressure vessel steel 15Cr2MoV(A) consequences for the assessment of reactor safetyBÖHMERT, J; BERGNER, F; GROSSE, M et al.Nuclear engineering and design. 1995, Vol 159, Num 2-3, pp 131-141, issn 0029-5493Conference Paper

Radiation stability of WWER RPV cladding materialsGILLEMOT, F; HORVATH, M; URI, G et al.International journal of pressure vessels and piping. 2007, Vol 84, Num 8, pp 469-474, issn 0308-0161, 6 p.Article

Usage of the small-punch-test for the characterisation of reactor vessel steels in the brittle-ductile transition regionLINSE, T; KUNA, M; SCHUHKNECHT, J et al.Engineering fracture mechanics. 2008, Vol 75, Num 11, pp 3520-3533, issn 0013-7944, 14 p.Conference Paper

Application of the normalization method for the determination of J-R curvesDZUGAN, J; VIEHRIG, H.-W.Materials science & engineering. A, Structural materials : properties, microstructure and processing. 2004, Vol 387-89, pp 307-311, issn 0921-5093, 5 p.Conference Paper

STUDY OF THE BELTLINE WELD AND BASE METAL OF WWER-440 FIRST GENERATION REACTOR PRESSURE VESSELSCHUHKNECHT, J; RINDELHARDT, U; VIEHRIG, H.-W et al.Strength of materials. 2010, Vol 42, Num 1, pp 70-77, issn 0039-2316, 8 p.Conference Paper

Some issues by using the master curve conceptVIEHRIG, H.-W; BOEHMERT, J; DZUGAN, J et al.Nuclear engineering and design. 2002, Vol 212, Num 1-3, pp 115-124, issn 0029-5493Conference Paper

Reconstitution techniques qualification and evaluation to study ageing phenomena of nuclear pressure vessel materials (RESQUE)VAN WALLE, E; SCIBETTA, M; VALO, M. J et al.Nuclear engineering and design. 2001, Vol 209, Num 1-3, pp 67-77, issn 0029-5493Conference Paper