Update of the nuclear criticality slide rule calculations: Studies with common shielding materials

T. M. Miller, C. Celik, C. Hopper, M. Duluc, D. Heinrichs, S. Kim, A. Brown, C. Wilson, M. Troisne

Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review

1 Scopus citations

Abstract

This paper presents preliminary results from the third phase of the current update to the nuclear criticality slide rule, in which MCNP, MAVRIC/Monaco, and COG have simulated the prompt neutron and photon dose from critical spheres of 4.95% enriched uranyl fluoride solution and 93.2% enriched uranium metal. New to this phase is the inclusion of various thicknesses of lead, steel, concrete, and water shielding. This phase also evaluated the effects of humidity on the unshielded configurations in the first phase, as well as the effects of changing the ground composition used in the first phase from concrete to dry soil. The small sample of results presented show that MCNP, MAVRIC/Monaco, and COG results are statistically the same or different by only a few percent. The impact of the shielding materials depends on their thickness, but doses decreased by nearly a factor of 100 are presented. In a few instances, buildup of gamma doses occurs due to neutron interactions in shielding materials.

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

The contribution to this work by ORNL was funded by the United States Department of Energy Nuclear Criticality Safety Program (NCSP). Notice: This manuscript has been authored by UT-Battelle, LLC, under contract DE-AC05-00OR22725 with the US Department of Energy (DOE). The US government retains and the publisher, by accepting the article for publication, acknowledges that the US government retains a nonexclusive, paid-up, irrevocable, worldwide license to publish or reproduce the published form of this manuscript, or allow others to do so, for US government purposes. DOE will provide public access to these results of federally sponsored research in accordance with the DOE Public Access Plan (http://energy.gov/downloads/doe-public-access-plan). This work was performed under the auspices of the US Department of Energy by Lawrence Livermore National Laboratory under Contract DE-AC52-07NA27344 and was funded by the US Department of Energy Nuclear Criticality Safety Program.

FundersFunder number
US Department of Energy
United States Department of Energy
U.S. Department of Energy
Lawrence Livermore National LaboratoryDE-AC52-07NA27344
Oak Ridge National Laboratory

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