TY - GEN
T1 - Update of the nuclear criticality slide rule calculations
T2 - 20th Topical Meeting of the Radiation Protection and Shielding Division, RPSD 2018
AU - Miller, T. M.
AU - Celik, C.
AU - Hopper, C.
AU - Duluc, M.
AU - Heinrichs, D.
AU - Kim, S.
AU - Brown, A.
AU - Wilson, C.
AU - Troisne, M.
N1 - Publisher Copyright:
© 2018 American Nuclear Society. All rights reserved.
PY - 2018
Y1 - 2018
N2 - 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.
AB - 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.
UR - http://www.scopus.com/inward/record.url?scp=85069700320&partnerID=8YFLogxK
M3 - Conference contribution
AN - SCOPUS:85069700320
T3 - 20th Topical Meeting of the Radiation Protection and Shielding Division, RPSD 2018
BT - 20th Topical Meeting of the Radiation Protection and Shielding Division, RPSD 2018
PB - American Nuclear Society
Y2 - 26 August 2018 through 31 August 2018
ER -