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Title: Ion irradiation testing of Improved Accident Tolerant Cladding Materials

This report summarizes the results of ion irradiations conducted on two FeCrAl alloys (named as ORNL A&B) for improving the accident tolerance of LWR nuclear fuel cladding. After irradiation with 1.5 MeV protons to ~0.5 to ~1 dpa and 300°C nanoindentations were performed on the cross-sections along the ion range. An increase in hardness was observed in both alloys. Microstructural analysis shows radiation induced defects.
Authors:
 [1] ;  [1] ;  [1]
  1. Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
Publication Date:
OSTI Identifier:
1114410
Report Number(s):
LA-UR--14-20235
TRN: US1500363
DOE Contract Number:
AC52-06NA25396
Resource Type:
Technical Report
Research Org:
Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)
Sponsoring Org:
USDOE National Nuclear Security Administration (NNSA)
Country of Publication:
United States
Language:
English
Subject:
36 MATERIALS SCIENCE; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; FUEL CANS; PROTONS; ATOMIC DISPLACEMENTS; IRRADIATION; MEV RANGE 01-10; IRON BASE ALLOYS; CHROMIUM ALLOYS; ALUMINIUM ALLOYS; TERNARY ALLOYS SYSTEMS; HARDNESS; MICROSTRUCTURE; TEMPERATURE RANGE 0400-1000 K; PHYSICAL RADIATION EFFECTS