An analysis of various solution strategies and perturbations on inputs of the reactor shielding problem

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Abstract

Previous work focused on the use of automated variance reduction parameters for use in a fixed source reactor shielding problem to solve for ex-core particle transport results. The current work assesses that strategy in light of a fully-coupled Monte Carlo problem run as a critical system with parallel processing and the use of moderate variance reduction parameters set manually. The results from the two strategies compare well. Also, results are compared between the MCNP, Virtual Environment for Reactor Applications (VERA) and Shift computer codes. Shift and VERA deliver similar results and compare well to MCNP. Scott Mosher of Oak Ridge National Laboratory assisted with questions on ADVANTG input, and Philip Tufts of Duke Energy spent long hours reviewing every input of the Harris Nuclear Plant base calculations. We appreciate the dedication and assistance. This research was also supported by CASL (www.casl.gov), an Energy Innovation Hub (http://www.energy.gov/hubs) for Modeling and Simulation of Nuclear Reactors under U.S. Department of Energy Contract No. DE-AC05-00OR22725. The authors would also like to acknowledge the development and user support provided by the Exnihilo and MPACT code development teams.

Original languageEnglish
Title of host publication20th Topical Meeting of the Radiation Protection and Shielding Division, RPSD 2018
PublisherAmerican Nuclear Society
ISBN (Electronic)9780894487460
StatePublished - 2018
Event20th Topical Meeting of the Radiation Protection and Shielding Division, RPSD 2018 - Santa Fe, United States
Duration: Aug 26 2018Aug 31 2018

Publication series

Name20th Topical Meeting of the Radiation Protection and Shielding Division, RPSD 2018

Conference

Conference20th Topical Meeting of the Radiation Protection and Shielding Division, RPSD 2018
Country/TerritoryUnited States
CitySanta Fe
Period08/26/1808/31/18

Funding

This research was also supported by CASL (www.casl.gov), an Energy Innovation Hub (http://www.energy.gov/hubs) for Modeling and Simulation of Nuclear Reactors under U.S. Department of Energy Contract No. DE-AC05-00OR22725.

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