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13篇 您的检索式：作者名="Niffenegger M"

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		题名	作者	年代	出处	被引量
	1	Integrity analysis of a reactor pressure vessel subjected to pressurized thermal shocks by considering constraint effect显示文摘	Qian G Niffenegger M	2013	Engineering Fracture Mechanics2013，，：	1
	2	Procedures, methods and computer codes for the probabilistic assessment of reactor pressure vessels subjected to pressurized thermal shocks 显示文摘	Qian G Niffenegger M	2013	Nuclear Engineering and Design2013，258，：	1
	3	Monitoring Fa tigue Degradation in Austenitie Stainless Steels显示文摘	Kalkhof D Grosse M Niffenegger M		0，，：	1
	4	A computational fatigue analysis of cyclic thermal shock in notched specimens显示文摘	Janssens K G F Niffenegger M Reichlin K	2009	Nuclear Engineering and Design2009，239，1：	1
	5	Procedures, methods and computer codes for the probabilistic assessment of reactor pressure vessels subjected to pressurized thermal shocks显示文摘	QIAN G NIFFENEGGER M	2013	Nuclear Engineering and Design2013，258，：	1
	6	Monitoring the embrittlement of reactor pressure vessel steels by using the Seeheck eoeffieient显示文摘	NIFFENEGGER M LEBER H	2009	J Nucl Mater2009，389，1：	1
	7	Probabilistic assessment of a reactor pressure vessel subjected to pressurized thermal shocks by using crack distributions显示文摘	QIAN G GONZ h LEZ-ALBUIXECH V F NIFFENEGGER M	2014	Nuclear Engineering and Design2014，270，：	1
	8	Probabilistic fracture assessment of piping systems based on FITNET FFS procedure显示文摘	QIAN G NIFFENEGGER M	2011	Nuclear Engineering and Design2011，241，3：	1
	9	Sensitivity of magnetiza-tion curves of different austenitic stainless tube andpipe steels to mechanical fatigue显示文摘	Niffenegger M Leber H J	2008	Journal of Nucle-ar Materials2008，377，：	1
	10	Probabilistic assessment of a reactor pressure vessel subjected to pressurized thermal shocks by using crack distributions显示文摘	QIAN G GONZ kLEZ-ALBUIXECH V F NIFFENEGGER M	2014	Nuclear Engineering and Design2014，270，：	1
	11	Procedures, methods and computer codes for the probabilistic assessment of reactor pressure vessels subjected to pressurized thermal shocks显示文摘	QIAN G NIFFENEGGER M	2013	Nuclear Engineering and Design2013，258，：	1
	12	Monitoring of low-cycle fatigue degradation in X6CrNiTi18-10 austenitic steel 显示文摘	GROSSE M NIFFENEGGER M KALKHOF D	2001	Journal of Nuclear Materials2001，296，：	1
	13	Influen- cing parameters on martensite transformation during low cycle fa- tigue for steel AISI 321显示文摘	GROSSE M KALKHOF D NIFFENEGGER M	2006	Materials Science and Engineering: A2006，437，1：	1

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