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.
Revised: July 27, 2010 |
Published: March 31, 2001
Citation
Greenwood L.R., and C.A. Baldwin. 2001.Neutron Dosimetry and Damage Calculations for the HFIR-RB-11J,12J Irradiations. In Fusion Materials: Semi-Annual Progress Report Ending December 31, 2001. 214-219. Washington Dc:US Department of Energy, Office of Fusion Energy Sciences.PNNL-SA-31901.