Microstructure of 316 Stainless Steel Cladding from a Fuel Pin Irradiated in EBR-II
| Autor: | F. M. Berting |
|---|---|
| Rok vydání: | 1977 |
| Předmět: | |
| Zdroj: | Proceedings, annual meeting, Electron Microscopy Society of America. 35:38-39 |
| ISSN: | 2690-1315 0424-8201 |
| Popis: | Swelling of the stainless steel cladding which contains the fuel in nuclear reactors is a well-known phenomenon. Efforts to minimize the swelling and prolong the life of the fuel pins depends on understanding the mechanisms by which swelling occurs. Study of the microstructural damage caused by neutron irradiation of the 316 stainless steel currently used in cladding is an important part of the investigation of the swelling mechanisms. Most of the microstructural investigations of swelling phenomena to date have been performed on material irradiated in isothermal capsules that eliminate contact between the samples and the fuel.This report is concerned with the steel actually used to contain the fuel pellets for a normal lifetime in-reactor. The pin cladding experienced the full range of temperatures and fluences characteristic of the 13.5" long reactor core. The conditions of irradiation for the fuel pin studied are shown in Figure 1(a), where temperature rises steadily from bottom to top of the pin and fluence reaches a peak at about core center. |
| Databáze: | OpenAIRE |
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