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Neutron Dosimetry and Damage Calculations for the HFIR-RB-11J,12J Irradiations

Book ·
OSTI ID:984268
Neutron fluence measurements and radiation damage calculations are reported for the joint U.S. Japanese experiments RB-11J and RB-12J which were conducted in the removable beryllium (RB) position of the High Flux Isotope Reactor (HFIR) at Oak Ridge National Laboratory (ORNL). These experiments employed a Eu2O3 thermal shield for the first time to reduce the thermal neutron fluence. The maximum total neutron fluence at midplane was 1.85x10^22 n/cm^2 (9.5x10^21 n/cm^2 above 0.1 MeV), resulting in about 5.5 dpa and 3.6 appm helium in type 316 stainless steel.
Research Organization:
Pacific Northwest National Laboratory (PNNL), Richland, WA (US)
Sponsoring Organization:
USDOE
DOE Contract Number:
AC05-76RL01830
OSTI ID:
984268
Report Number(s):
PNNL-SA-31901; AT6020100
Country of Publication:
United States
Language:
English