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Title: Standardization of accelerator irradiation procedures for simulation of neutron induced damage in reactor structural materials

Self-ion irradiation is widely used as a method to simulate neutron damage in reactor structural materials. Accelerator-based simulation of void swelling, however, introduces a number of neutron-atypical features which require careful data extraction and, in some cases, introduction of innovative irradiation techniques to alleviate these issues. In this paper, we briefly summarize three such atypical features: defect imbalance effects, pulsed beam effects, and carbon contamination. The latter issue has just been recently recognized as being relevant to simulation of void swelling and is discussed here in greater detail. It is shown that carbon ions are entrained in the ion beam by Coulomb force drag and accelerated toward the target surface. Beam-contaminant interactions are modeled using molecular dynamics simulation. Finally, by applying a multiple beam deflection technique, carbon and other contaminants can be effectively filtered out, as demonstrated in an irradiation of HT-9 alloy by 3.5 MeV Fe ions.
Authors:
ORCiD logo [1] ;  [1] ;  [2] ;  [1] ;  [1] ;  [3] ;  [4]
  1. Texas A & M Univ., College Station, TX (United States). Dept. of Nuclear Engineering
  2. Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
  3. Texas A & M Univ., College Station, TX (United States). Dept. of Nuclear Engineering; Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
  4. Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
Publication Date:
Report Number(s):
LA-UR-17-25080
Journal ID: ISSN 0168-583X; TRN: US1800805
Grant/Contract Number:
AC52-06NA25396; NE0008297
Type:
Accepted Manuscript
Journal Name:
Nuclear Instruments and Methods in Physics Research. Section B, Beam Interactions with Materials and Atoms
Additional Journal Information:
Journal Volume: 409; Journal ID: ISSN 0168-583X
Publisher:
Elsevier
Research Org:
Texas A & M Univ., College Station, TX (United States); Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
Sponsoring Org:
USDOE Office of Nuclear Energy (NE)
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; ion irradiation; beam contamination; carbon
OSTI Identifier:
1415407