Swelling in previously neutron-irradiated commercial Fe-Cr-Ni based alloys under electron irradiation
| Autor: | J.J. Laidler, L.E. Thomas, D.S. Gelles |
|---|---|
| Rok vydání: | 1982 |
| Předmět: |
Nuclear and High Energy Physics
Materials science technology industry and agriculture Nimonic equipment and supplies Microstructure Fluence Nuclear Energy and Engineering medicine Radiation damage Electron beam processing General Materials Science Neutron Irradiation Swelling medicine.symptom Composite material |
| Zdroj: | Journal of Nuclear Materials. :504-514 |
| ISSN: | 0022-3115 |
| DOI: | 10.1016/0022-3115(82)90522-0 |
| Popis: | In order to avoid the artifacts which result because void swelling and precipitate stability are not accelerated to the same degree during radiation damage simulation experiments, a series of electron irradiation experiments were performed on commercial alloy specimens which were first irradiated in-reactor. This procedure is intended to establish a microstructure typical of in-reactor behavior which is then irradiated at accelerated rates in order to provide prediction of behavior to high fluence in-reactor on a reduced time scale. Neutron-irradiated specimens of fully-aged and solution treated Nimonic ∗ PE16, 20% cold-worked AISI 310 stainless steel and aged A-286 were electron irradiated at 500–700°C in the HVEM to determine the effect of reactor-conditioning on the simulation of void swelling at high neutron fluences. For aged PE16 it was found that the swelling behavior under electron irradiation was unaffected by prior neutron irradiation. Specimens from four different reactor temperature/fluence conditions showed the same temperature-dependent swelling rates in the HVEM irradiations. The swelling behavior of aged PE16. A-286 and cold-worked 310 was also consistent with previous results on specimens which were not previously neutron irradiated. However, reactor conditioning did alter the swelling response of solution-treated PE16 under electron irradiation, and this effect is attributed to the irradiaton-enhanced precipitation of γ' which occurs in-reactor. It is concluded that void and dislocation substructures generated in-reactor exert only second order control over void swelling during electron irradiation. Reactor conditioning expriments can be better described as temperature change experiments, providing that the alloy in question remains stable during neutron irradiation. |
| Databáze: | OpenAIRE |
| Externí odkaz: |
|