Skip Nav Destination
Close Modal
Update search
Filter
- Title
- Author
- Author Affiliations
- Full Text
- Abstract
- Keyword
- DOI
- ISBN
- ISBN-10
- ISSN
- EISSN
- Issue
- Journal Volume Number
- References
- Conference Volume Title
- Paper No
Filter
- Title
- Author
- Author Affiliations
- Full Text
- Abstract
- Keyword
- DOI
- ISBN
- ISBN-10
- ISSN
- EISSN
- Issue
- Journal Volume Number
- References
- Conference Volume Title
- Paper No
Filter
- Title
- Author
- Author Affiliations
- Full Text
- Abstract
- Keyword
- DOI
- ISBN
- ISBN-10
- ISSN
- EISSN
- Issue
- Journal Volume Number
- References
- Conference Volume Title
- Paper No
Filter
- Title
- Author
- Author Affiliations
- Full Text
- Abstract
- Keyword
- DOI
- ISBN
- ISBN-10
- ISSN
- EISSN
- Issue
- Journal Volume Number
- References
- Conference Volume Title
- Paper No
Filter
- Title
- Author
- Author Affiliations
- Full Text
- Abstract
- Keyword
- DOI
- ISBN
- ISBN-10
- ISSN
- EISSN
- Issue
- Journal Volume Number
- References
- Conference Volume Title
- Paper No
Filter
- Title
- Author
- Author Affiliations
- Full Text
- Abstract
- Keyword
- DOI
- ISBN
- ISBN-10
- ISSN
- EISSN
- Issue
- Journal Volume Number
- References
- Conference Volume Title
- Paper No
NARROW
Format
Article Type
Subject Area
Topics
Date
Availability
1-3 of 3
Keywords: boiling water reactor
Close
Follow your search
Access your saved searches in your account
Would you like to receive an alert when new items match your search?
Sort by
Journal Articles
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. February 2013, 135(1): 011206.
Paper No: PVT-12-1003
Published Online: December 17, 2012
... boiling water reactors under design transients, described in the final safety analysis report (FSAR), the PFM analysis code: FAVOR, which has been verified by USNRC, is adopted in this work. Actual geometries, material properties, alloying elements, neutron fluence, and operating conditions are used...
Journal Articles
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. August 2007, 129(3): 460–467.
Published Online: August 28, 2006
... in light water reactors. The crack growth behavior of sensitized type 304 stainless steel with a 1T-CT specimen in simulated boiling water reactor (BWR) environments is analyzed based on this approach. The effect of several environmental, material, and mechanical parameters on the EAC crack growth rate...
Journal Articles
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. August 2006, 128(3): 318–327.
Published Online: August 8, 2005
... mechanism. 25 04 2004 08 08 2005 stress corrosion cracking nickel alloys deformation oxidation yield strength fission reactors stress corrosion cracking crack growth rate nickel-base alloy alloy 600 light water reactor pressurized water reactor boiling water reactor...
