A phenomenological investigation of in-reactor cracking of type 304 stainless steel control rod cladding
- 1 May 1989
- journal article
- Published by Elsevier in Nuclear Engineering and Design
- Vol. 113 (3) , 297-321
- https://doi.org/10.1016/0029-5493(89)90024-1
Abstract
No abstract availableKeywords
This publication has 3 references indexed in Scilit:
- Radiation induced phosphorus segregation in austenitic and ferritic alloysJournal of Nuclear Materials, 1984
- Liquid metal embrittlement of nuclear materialsJournal of Nuclear Materials, 1980
- Impurity adsorption and intergranular corrosion of austenitic stainless steel in boiling HNO3-K2Cr2O7 solutionsCorrosion Science, 1967