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Neutron dosimetry, damage calculations, and helium measurements for the HFIR-MFE-60J-1 and MFE-330J-1 spectral tailoring experiments

Technical Report ·
DOI:https://doi.org/10.2172/114924· OSTI ID:114924
 [1];  [2];
  1. Pacific Northwest Laboratory, Richland, WA (United States)
  2. Oak Ridge National Lab., TN (United States)
The objective is to provide dosimetry and damage analysis for fusion materials irradiation experiments. Neutron fluence measurements and radiation damage calculations are reported for the joint US -Japanese MFE-60J-1 and MFE-330J-1 experiments in the hafnium-lined removable beryllium (RB{sup *}) position of the High Flux Isotope Reactor (HFIR) at Oak Ridge National Laboratory. These experiments were continuations of the ORR-6J and 7J irradiations performed in the Oak Ridge Research Reactor. The combination of irradiations was designed to tailor the neutron spectrum in order to achieve fusion reactor helium/dpa levels in stainless steel. These experiments produced maximum helium (appm)/dpa(displacement per atom) levels of 10.2 at 18.5 dpa for the ORR-6J and HFIR-MFE-60J-1 combination and 11.8 at 19.0 dpa for the ORR-7J and HFIR-MFE-330J-1 combination. A helium measurement in one JPCA sample was in good agreement with helium calculations.
Research Organization:
Oak Ridge National Lab., TN (United States)
DOE Contract Number:
AC06-76RL01830
OSTI ID:
114924
Report Number(s):
DOE/ER--0313/17; ON: DE95013663
Country of Publication:
United States
Language:
English