국내 방사성폐기물 처분 환경을 고려한 RI 폐기물 고화체 방사선 조사량 설정을 위한 예비 평가
Preliminary Evaluation for Setting irradiation Criteria for Encapsulated Radioactive Isotope Waste form Considering Conditions of LILW Disposal Facility in Korea
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Radioactive isotope waste generated from the medical, industrial, and research sectors in Korea mustbe safely managed to minimize potential impacts on humans and the ecosystem. For this, radioactive waste needs tobe safely disposed of in disposal facilities. However, due to the absence of treatment methodologies and technologiesfor radioactive isotope waste that guarantee the safety and long-term stability of disposal facilities in Korea, thewaste is currently being stored long-term in the radioactive waste building within disposal sites without proper finaldisposal solutions. To address this challenge, the development of encapsulation treatment technologies is underway. This study assesses the absorbed dose of encapsulated waste forms using the MCNP computational code, reflectingthe specific conditions of domestic disposal facilities, in order to establish irradiation testing criteria for waste formspost-encapsulation. The study modeled two scenarios: one with a uniformly distributed radioactivity environmentand another a “Hot Spot” environment where radioactivity is concentrated in a specific area, assuming a cumulativeradiation period of 300 years. The results showed an absorbed dose of 4.89 ×103 Gy in the uniform distributionenvironment and 2.83 × 105 Gy in the Hot Spot environment. These results did not exceed the irradiation testingcriteria (1.0 × 107 Gy) set by the U.S. NRC, confirming that encapsulated waste form containing inorganic materialssuch as sealed sources does not require irradiation testing. However, for encapsulated waste form containing organicmaterials, such as animal carcasses or organic liquids, irradiation testing is required. Based on the evaluationconsidering the domestic disposal environment, it is proposed to set the irradiation testing criteria at 5.0 × 105 Gy. Thisstudy provides crucial foundational data for revising acceptance criteria for the safe disposal of radioactive isotopewaste and is expected to contribute to establishing irradiation testing criteria suitable for the domestic disposalenvironment.
Abstract
Radioactive isotope waste generated from the medical, industrial, and research sectors in Korea mustbe safely managed to minimize potential impacts on humans and the ecosystem. For this, radioactive waste needs tobe safely disposed of in disposal facilities. However, due to the absence of treatment methodologies and technologiesfor radioactive isotope waste that guarantee the safety and long-term stability of disposal facilities in Korea, thewaste is currently being stored long-term in the radioactive waste building within disposal sites without proper finaldisposal solutions. To address this challenge, the development of encapsulation treatment technologies is underway. This study assesses the absorbed dose of encapsulated waste forms using the MCNP computational code, reflectingthe specific conditions of domestic disposal facilities, in order to establish irradiation testing criteria for waste formspost-encapsulation. The study modeled two scenarios: one with a uniformly distributed radioactivity environmentand another a “Hot Spot” environment where radioactivity is concentrated in a specific area, assuming a cumulativeradiation period of 300 years. The results showed an absorbed dose of 4.89 ×103 Gy in the uniform distributionenvironment and 2.83 × 105 Gy in the Hot Spot environment. These results did not exceed the irradiation testingcriteria (1.0 × 107 Gy) set by the U.S. NRC, confirming that encapsulated waste form containing inorganic materialssuch as sealed sources does not require irradiation testing. However, for encapsulated waste form containing organicmaterials, such as animal carcasses or organic liquids, irradiation testing is required. Based on the evaluationconsidering the domestic disposal environment, it is proposed to set the irradiation testing criteria at 5.0 × 105 Gy. Thisstudy provides crucial foundational data for revising acceptance criteria for the safe disposal of radioactive isotopewaste and is expected to contribute to establishing irradiation testing criteria suitable for the domestic disposalenvironment.