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- W4382357866 abstract "neutron energy E. A standalone Fortran code has been developed that generates the OTF library for any isotope that can be processed by NJOY. The OTF cross sections agree with the NJOY-based cross sections for all neutron energies and all temperatures in the range specified by the user, e.g., 250K - 3200K. The OTF methodology has been successfully implemented into the MCNP Monte Carlo code and has been tested on several test problems by comparing MCNP with conventional ACE cross sections versus MCNP with OTF cross sections. The test problems include the Doppler defect reactivity benchmark suite and two full-core VHTR configurations, including one with multiphysics coupling using RELAP5-3D/ATHENA for the thermal-hydraulic analysis. The comparison has been excellent, verifying that the OTF libraries can be used in place of the conventional ACE libraries generated at problem temperatures. In addition, it has been found that using OTF cross sections greatly reduces the complexity of the input for MCNP, especially for full-core temperature feedback calculations with many temperature regions. This results in an order of magnitude decrease in the number of input lines for full-core configurations, thus simplifying input preparation and reducing the potential for input errors. Finally, for full-core problems with multiphysics feedback, the memory required to store the cross section data is considerably reduced with OTF cross sections and the additional computational effort to use OTF cross sections is negligible. This is a joint project with the University of Michigan, Argonne National Laboratory, and Los Alamos National Laboratory." @default.
- W4382357866 created "2023-06-29" @default.
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- W4382357866 date "2023-05-23" @default.
- W4382357866 modified "2023-09-24" @default.
- W4382357866 title "On-the-Fly Energy Condensation for Whole-Core Multiphysics Simulations" @default.
- W4382357866 doi "https://doi.org/10.2172/1986215" @default.
- W4382357866 hasPublicationYear "2023" @default.
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