Radiological analysis of transport and storage container for very low-level liquid radioactive waste

Authors :: Youn Jun Kim
Un Jang Lee
Seung Hun Shin
Hye Min Park
Woo Nyun Choi
Seungbin Yoon
Seong Hee Park
Hee Reyoung Kim
Source :: Nuclear Engineering and Technology, Vol 53, Iss 12, Pp 4137-4141 (2021)
Publication Year :: 2021
Publisher :: Elsevier, 2021.
Abstract: As NPPs continue to operate, liquid waste continues to be generated, and containers are needed to store and transport them at low cost and high capacity. To transport and store liquid phase very low-level radioactive waste (VLLW), a container is designed by considering related regulations. The design was constructed based on the existing container design, which easily transports and stores liquid waste. The radiation shielding calculation was performed according to the composition change of barium sulfate (BaSO4) using the Monte Carlo N-Particle (MCNP) code. High-density polyethylene (HDPE) without mixing the additional BaSO4, represented the maximum dose of 1.03 mSv/hr (

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