Reactor vessel cladding separate effects studies
- 1 January 1987
- journal article
- Published by Elsevier in Nuclear Engineering and Design
- Vol. 98 (2) , 171-193
- https://doi.org/10.1016/0029-5493(87)90165-8
Abstract
No abstract availableKeywords
This publication has 4 references indexed in Scilit:
- Fracture toughness of austenitic stainless steel weld metal at 4 KPublished by Office of Scientific and Technical Information (OSTI) ,1984
- Applicability of LEFM to the analysis of PWR vessels under LOCA-ECC thermal shock conditionsPublished by Office of Scientific and Technical Information (OSTI) ,1978
- Metallographic investigation on the cladding failure in the pressure vessel of a BWRNuclear Engineering and Design, 1971
- Impact Strength of Austenitic Stainless-Steel Welds at −320 F—Effects of Composition, Ferrite Content, and Heat-TreatmentJournal of Basic Engineering, 1966