Swelling in several commercial alloys irradiated to very high neutron fluence

Abstract

HMSTB/ Di srRi sunoN OF liiis mfmnj is mi Mi TEO NOTICE This report was prepared as an account of work sponsored by the United States Government. Neither the United States nor the U.S. Department of Energy (DOE), nor any of its employes, nor any of its contractors, subcontractors or their employes, makes any warranty, expressed or implied, or assumes any legal liability or responsibility for any third party's use or the results of such use of any information, apparatus, product or process disclosed in this report, or represents that its use by such third party would not infringe privately owned rights. ..,. I 7.1 SWELLING IN SEVERAL COM^€RCIAL ALLOYS IRRADIATED TO VERY HIGH NEUTRON FLUENCE-D. S. Gelles and J. S. Pintler (Westinghouse Hanford Company) 7.1.1 ADIP Task The Department of Energy (OOE)/Office of Fusion Energy (OFE) has cited the need to investigate ferritic alloys under the ADIP program task, Ferritic Steels Development (Path E). The tasks involved are akin to task number 1.C.2, Microstructures and Swelling in Austenitic Alloys and task number l.C.l, Microstructural Stability. 7.1.2 Objective The objective of this work is to provide guidance on the applicability of martensitic stainless steels for fusion reactor structural components. 7.1.3 Summary Swelling values have been obtained from a set of commercial alloys irradiated in EBR-II to a peak fluence of 2.5 x 10^3 n/cn^ (E > 0.1 MeV) or ^,125 dpa covering the range 400 to SSO'C. The alloys can be ranked for swelling resistance from highest to lowest as follows: the martensitic and ferritic alloys, the niobium based alloys, the precipitation strengthened iron and nickel based alloys, the molybdenum alloys and the austenitic alloys.

Effect of high dose/high temperature irradiation on the microstructure of heat resistant 11Cr ferritic/martensitic steels

“…The fact that the radiation-induced void swelling at 405°C to 94.6 dpa was ffi0.05% was thought to be consistent with the result that the HT9 irradiated in FFTF to over 200 dpa at 400-420°C was <2% [4,5]. As indicated in previous studies on void swelling of 12Cr F/M steels including the HT9 [3][4][5][6][7][8][9][10], it can be deduced that peak void swelling of the PNC-FMS was lying in the temperature range of 400-425°C or that of lower side [11,12].…”

Helium effects on void formation in 9Cr-1MoVNb and 12Cr-1MoVW irradiated in HFIR

“…The U.S. magnetic fusion reactor (MFR) materials program included these steels as structural candidates in 1979 [7]. Void swelling resistance has been demonstrated more recently for various ferritic steels irradiated in FBRs to doses as high as 120 to 150 dpa [8]- [12]. However, helium generation in ferritic steels is very low (~0.1 appm He/dpa) in FBRs such as EBR-II, as seen in Fig.…”

Radiation Effects in Nickel-Based Alloys

“…Irradiation temperatures in these experiments ranged from about 400 to 650 C. Initial data for a range of commercial alloys, including ferritic and austenitic steels, as well as nickel-based alloys, were reported by Bates and Powell 19 and Powell et al, 20 with higher dose data (up to a peak fluence (E > 0.1 MeV) of $25 Â 10 26 n m À2 , corresponding to $125 dpa) being reported by Gelles 21 and Garner and Gelles. Irradiation temperatures in these experiments ranged from about 400 to 650 C. Initial data for a range of commercial alloys, including ferritic and austenitic steels, as well as nickel-based alloys, were reported by Bates and Powell 19 and Powell et al, 20 with higher dose data (up to a peak fluence (E > 0.1 MeV) of $25 Â 10 26 n m À2 , corresponding to $125 dpa) being reported by Gelles 21 and Garner and Gelles.…”