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It is necessary to verify (and validate when experimental data are available) shielding codes and methodologies for Molten Salt Reactors (MSRs). This paper examines the impact of using a fine and coarse multigroup cross section library vs. the reference continuous energy data. Molten Salt Research Reactor (MSRR) being developed by the NEXT Research Alliance (NEXTRA) is used as a testbed. Shielding analyses are performed in support of MSRR development using the MAVRIC sequence of the SCALE 6.2.4 code package. The sequence uses deterministic forward and adjoint radiation transport calculations with FW-CADIS methodology to generate variance reduction parameters that are used by MONACO, a fixed source Monte Carlo code. Originally, MONACO was developed as a multigroup code, and a 200-group and 27-group neutron shielding-focused libraries were provided as part of the package. While the 200-group library provides adequate accuracy for many applications, it is highly desirable to confirm this for any specific analysis. In SCALE 6.2, continuous energy capability was implemented in MONACO, thus enabling direct and consistent evaluation and quantification of the impact of using a multigroup rather than the reference continuous energy library. This paper examines the impact of multigroup approximation on main radiation environment parameters in MSRR shielding analysis, including the fast flux and dpa.

The research presented herein outlines a comprehensive process for characterizing the major radiological source terms necessary for radiation protection and licensing activities that one would expect in a liquid-fueled molten salt reactor. This process leverages organic simulation tools in the SCALE modeling and simulation code suite to provide an "off-the-shelf" solution for shielding assessments of this reactor type. Ultimately, this source development process is applied to a representative molten salt reactor system to assess the impact of ex-core source terms on shielding in varying operating conditions. The results of the analysis determined that while the prompt core source is the major dose contributor outside the radiological shielding, specific ex-core features, such as the primary salt loop components and configuration, can have an appreciable dose impact, and thus must be accounted for. [ABSTRACT FROM AUTHOR]