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Overview of Shielding Analyses at Oak Ridge National Laboratory’s Spallation Neutron Source Second Target Station

Publication Type
Conference Paper
Book Title
SATIF-15: 15th Workshop on Shielding aspects of Accelerators, Targets, and Irradiation Facilities. Session 1: Facility Reports / Shielding & Dosimetry.
Publication Date
Page Numbers
13 to 24
Publisher Location
Paris, France
Conference Name
Conference Location
East Lansing, Michigan, United States of America
Conference Sponsor
Conference Date

The Neutronics Group of the Second Target Station project at Oak Ridge National Laboratory is responsible for all neutronics analyses related to design and construction. This paper provides an overview of four neutronics analyses performed for the Second Target Station project, which is representative of all the ongoing work but especially tasks related to shielding. These analyses extend from the proton accelerator through the target monolith and bunker to the end of a neutron beamline. Each example highlights the tools and methods the Neutronics Group uses for analysis. The primary tool is the Monte Carlo radiation transport code MCNP 6.2, but this is augmented by other codes that supplement the input of MCNP. The other codes specifically highlighted in this paper include Attila4MC, ADVANTG, and AARE.