Calculations vs. measurements of remnant dose rates for SNS spent structures

Conference · Fri Jun 01 04:00:00 EDT 2018

DOI:https://doi.org/10.1088/1742-6596/1046/1/012013· OSTI ID:1456786

Popova, Irina I. ^[1]; Gallmeier, Franz X. ^[1]; Trotter, Steven M. ^[1]; Dayton, Michael J. ^[1]

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1. ORNL

Residual dose rate measurements were conducted on target vessel #13 and proton beam window #5 after extraction from their service locations. These measurements were used to verify calculation methods of radionuclide inventory assessment that are typically performed for nuclear waste characterization and transportation of these structures. Neutronics analyses for predicting residual dose rates were carried out using the transport code MCNPX and the transmutation code CINDER90. For transport analyses complex and rigorous geometry model of the structures and their surrounding are applied. The neutronics analyses were carried out using Bertini and CEM high energy physics models for simulating particles interaction. Obtained preliminary calculational results were analysed and compared to the measured dose rates and overall are showing good agreement with in 40% in average.

• Research Organization: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: USDOE Office of Science (SC), Basic Energy Sciences (BES) (SC-22)
• DOE Contract Number: AC05-00OR22725
• OSTI ID: 1456786
• Country of Publication: United States
• Language: English