Published September 15, 2006 | Version v1
Journal article

Tensile testing of EP-823 and HT-9 after irradiation in STIP II

  • 1. MST-8, MS H816, Los Alamos National Laboratory, Los Alamos, NM 87545 (United States)
  • 2. MS K575, NMT-11, Los Alamos National Laboratory, Los Alamos, NM 87545 (United States)
  • 3. MS G742, D-5, Los Alamos National Laboratory, Los Alamos, NM 87545 (United States)
  • 4. Paul Scherrer Institut, Spallation Neutron Source Division, CH-52, Villigen-PSI (Switzerland)

Description

The predicted operating conditions for a lead-bismuth eutectic target to be used in an accelerator driven system for the Advanced Fuel Cycle Initiative spans a temperature range of 300-600 deg. C while being irradiated by a high energy (∼600 MeV) proton beam. Such spallation conditions lead to high displacement rates coupled with high accumulation rates of helium and hydrogen up to 150 appm/dpa. Two candidate ferritic/martensitic materials for these applications include HT-9 and EP-823. To investigate the effect of irradiation on these materials, the tensile properties were measured at 25, 250, and 400 deg. C after irradiation in the STIP II irradiation to doses up to 20 dpa at temperatures up to 350 deg. C. Losses in ductility concomitant with increases in yield stress are observed in both alloys although the embrittlement is more severe in the EP-823. This stronger embrittlement is attributed to the high silicon content in EP-823

Additional details

Identifiers

DOI
10.1016/j.jnucmat.2006.05.003;
PII
S0022-3115(06)00243-1;

Publishing Information

Journal Title
Journal of Nuclear Materials
Journal Volume
356
Journal Issue
1-3
Journal Page Range
p. 56-61
ISSN
0022-3115
CODEN
JNUMAM

Conference

Title
7. international workshop on spallation materials technology
Dates
29 May - 3 Jun 2005
Place
Thun (Switzerland)

Optional Information

Copyright
Copyright (c) 2006 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.