Assessing shielding material Performance: Benchmarking of Monte Carlo codes for oil shale and Basalt-Boron fiber concretes Hando Tohver a,* , Andrius Slavickas b , Maryna Holiuk c , Andrejs Krasn¸ i
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https://hdl.handle.net/10037/32531Dato
2023-12-12Type
Journal articleTidsskriftartikkel
Peer reviewed
Forfatter
Tohver, Hando; Motlep, Riho; Krasnikovs, Andrejs; Novakova, Iveta; Gulik, Volodymyr; Slavickas, Andrius; Holiuk, Maryna; Vaišnoras, MindaugasSammendrag
Cement-based concretes are commonly used for managing radioactive waste due to their low cost and radiation shielding properties. However, the potential of using
oil shale ash as an additive in waste packaging material has been overlooked. This study focuses on benchmarking and developing a Monte Carlo based modeling
methodology using multiple transport codes (MCNP, SERPENT, SCALE, OpenMC, and EGSnrc) to assess the effects of these additives on the gamma and neutron
shielding properties of concrete. The cross-code comparison showed that all transport codes are in excellent agreement with each other. Investigations into oil shale
ash demonstrated similar properties to fly ash. The addition of oil shale ash had a negligible effect on low-level waste (LLW) gamma shielding properties and a minor
negative effect on neutron shielding properties. The addition of basalt-boron fibers indicated a minor negative effect on LLW gamma shielding properties but a
significant positive effect on neutron shielding properties. The presence of basalt-boron fibers considerably decreased the photon flux resulting from the activation of
concrete. In conclusion, this study offers valuable insights into utilizing radiation transport codes to analyze the interactions between radiation particles and
innovative concrete additives.
Forlag
ElsevierSitering
Tohver, Motlep, Krasnikovs, Novakova, Gulik. Assessing shielding material Performance: Benchmarking of Monte Carlo codes for oil shale and Basalt-Boron fiber concretes Hando Tohver a,* , Andrius Slavickas b , Maryna Holiuk c , Andrejs Krasn¸ i. Nuclear Engineering and Design. 2023Metadata
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