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Evaluation of Radiation Impact on the Material of Outer Shielding Wall of Transportable Micro Reactor Using Monte Carlo Method

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A transportable micro reactor is a type of reactor that can move to the location where power is neededbased on demand.A shield that requires significant construction time and expenses, like a concrete containmentbuilding, might not be appropriate if it is expected that the external shield will be moved and operated for a shortperiod of time before being re-operated at a different location. This is why a radiation impact assessment must bedone when using a single material as a shielding wall. A transportable molten salt reactor under development wasselected as a reference system for the single material shielding study. The initial reactivity value of the designedtransportable micro reactor was estimated to be around 1.0577, and the error was calculated to be 0.00071. Accordingto the 1 m shielding wall investigation, earth and sand performed poorly in terms of neutron shielding. The othermaterials - concrete, rock and water - exhibited below normal background level doses, suggesting that they maybe used as shielding walls. There are significant differences in gamma shielding between materials. This is due tothe fact that gamma shielding has a density-dependent shielding capacity. A series of dose calculations outside theshielding wall generated a bounding line that indicate the point at which the radiation fell below the normal levelof 0.1 μSvh-1. Water is the shielding material that needs the greatest distance from the shielding wall, requiring adistance of 12.24 meters, while rock requires the least distance, 5.4 meters. Rock will therefore be the best material ifshielding is thought of utilizing single material.

Abstract

A transportable micro reactor is a type of reactor that can move to the location where power is neededbased on demand.A shield that requires significant construction time and expenses, like a concrete containmentbuilding, might not be appropriate if it is expected that the external shield will be moved and operated for a shortperiod of time before being re-operated at a different location. This is why a radiation impact assessment must bedone when using a single material as a shielding wall. A transportable molten salt reactor under development wasselected as a reference system for the single material shielding study. The initial reactivity value of the designedtransportable micro reactor was estimated to be around 1.0577, and the error was calculated to be 0.00071. Accordingto the 1 m shielding wall investigation, earth and sand performed poorly in terms of neutron shielding. The othermaterials - concrete, rock and water - exhibited below normal background level doses, suggesting that they maybe used as shielding walls. There are significant differences in gamma shielding between materials. This is due tothe fact that gamma shielding has a density-dependent shielding capacity. A series of dose calculations outside theshielding wall generated a bounding line that indicate the point at which the radiation fell below the normal levelof 0.1 μSvh-1. Water is the shielding material that needs the greatest distance from the shielding wall, requiring adistance of 12.24 meters, while rock requires the least distance, 5.4 meters. Rock will therefore be the best material ifshielding is thought of utilizing single material.

참고문헌 (6)

  1. Chung KW, "Shielding Considerations for a Transportable Microreactor", International Conference of Asian Political Parties (2023)
  2. Kulesza Joel A, "MCNP® Code Version 6.3.0 Theory & User Manual", United States, ~ (2022)
  3. Seo JU, "A study on the depletion behavior of molten salt reactor with OpenMC code", Transactions of the Korean Nuclear Society, ~ (2022)
  4. Yoon SJ, "Multi-layer Shielding Design for SmallSized Molten Salt Fast Reactor", International Conference of Asian Political Parties (2023)
  5. Compendium of Material Composition Data for Radiation Transport Modeling Richland, "Detwiler RS", Pacific Northwest National Laboratory, ~ (2021)
  6. Enforcement Decree of the Nuclear Safety Act, "Republic of Korea, Presidential Decree No. 2017 27972", ~ (2017)

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