中国机械工程学会生产工程分会知识服务平台

期刊


ISSN0308-0161
刊名International Journal of Pressure Vessels and Piping
参考译名国际压力容器与管道杂志
收藏年代1998～2024



全部

1998 1999 2000 2001 2002 2003
2004 2005 2006 2007 2008 2009
2010 2011 2012 2013 2014 2015
2016 2017 2018 2019 2020 2021
2022 2023 2024

2000, vol.77, no.1 2000, vol.77, no.10 2000, vol.77, no.11 2000, vol.77, no.12 2000, vol.77, no.13 2000, vol.77, no.14-15
2000, vol.77, no.2-3 2000, vol.77, no.4 2000, vol.77, no.5 2000, vol.77, no.6 2000, vol.77, no.7 2000, vol.77, no.8
2000, vol.77, no.9

题名作者出版年年卷期
A microstructural examination of irradiated reactor pressure vessel weld samplesP. J. E. Bischler; V. M. Callen; R. C. Corcoran; P. Spellward20002000, vol.77, no.10
Application of the master curve in the ASME codeS. T. Rosinski; W. L. Server20002000, vol.77, no.10
Direct measurement of reactor pressure vessel steels fracture toughness: master curve concept and instrumented Charpy-V testM. Serrano; F. J. Perosanz; J. Lapena20002000, vol.77, no.10
Examination of VVER-440 RPV steel re-irradiation behavior using materials from operating unitsYa. I. Shtrombakh20002000, vol.77, no.10
Irradiation surveillance data for an A508 forging and associated weld metalR. H. Priest; W. P. A. Belcher; C. M. Mendes; B. K. Neale20002000, vol.77, no.10
JAPEIC's activity on aging issue related to neutron irradiation of RPV/RV materialsS. Kataoka; T. Otsuka20002000, vol.77, no.10
Master curve characterization of the fracture toughness in unirradiated and irradiated RPV steels using full- and 1/3-size pre-cracked Charpy specimensB. -S. Lee; J. -H. Hong; W. -J. Yang; M. -Y. Huh; S. -H. Chi20002000, vol.77, no.10
Re-embrittlement behaviour of VVER-440 reactor pressure vessel weld material after annealingJ. Kohopaa; R. Ahlstrand20002000, vol.77, no.10
Results and evaluations of irradiation surveillance programmes of lightwater reactors in GermanyR. Langer; W. Backfisch; R. Bartsch20002000, vol.77, no.10



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