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Low level radioactive waste final disposal

Last Update: Jan 16, 2025
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 Safety Regulation for Final Disposal Facilities of Low-Level Radioactive Waste

Low level radioactive waste (LLRW) primarily originates from contaminated clothing, tools, and discarded components from nuclear power plants, accounting for approximately 90% of such waste. The remaining 10% comes from medical, agricultural, industrial, and research applications involving small-scale radioactive sources. The primary radionuclides present in LLRW are cobalt and cesium, which decay to levels comparable to background radiation within approximately 300 years. According to the Nuclear Materials and Radioactive Waste Management Act, the annual effective dose from LLRW disposal facilities to the general public must not exceed 0.25 millisieverts—one-fourth of the annual dose limit for individuals.

 Adopting a Multi-Barrier Design Concept for Final Disposal

The multi-barrier design employs disposal containers, engineered barriers, and natural barriers to isolate radioactive waste from human living environments.

 International Examples of LLRW Disposal Facilities

Major nuclear-powered countries such as the United States, Japan, France, Sweden, Finland, South Korea, and Spain have constructed final disposal facilities for LLRW. Currently, there are more than 100 operational disposal facilities worldwide. Most utilize near-surface disposal methods, followed by tunnel-based disposal, with a few employing deep geological disposal. These facilities operate safely and reliably.

The design of LLRW disposal facilities varies based on the type of radioactive waste stored and the geographical environment. Common types include trench disposal, concrete vault disposal, tunnel disposal, and deep geological disposal.

 Safety Regulation for Final Disposal Facilities of LLRW

The Nuclear Safety Commission (NSC) has established the " Regulations on Final Disposal of Low Level Radioactive Waste and Safety Management of the Facilities," which stipulate that disposal facilities cannot be located in the following areas:
  • Active fault zones or regions where geological conditions could compromise facility safety.
  • Areas with geochemical conditions that hinder the containment of radioactive contamination and affect facility safety.
  • Regions where surface or groundwater conditions could impact facility safety.
  • Densely populated areas.
  • Areas legally restricted from development.
As an independent safety regulatory authority, the NSC will continue to require the Ministry of Economic Affairs (MOEA) to urge Taiwan Power Company (TPC) to conduct site selection for LLRW actively. Additionally, it will reference successful international examples of public communication to improve engagement strategies and gain public acceptance.

 Technical Safety Regulation of LLRW Disposal Facilities

The NSC supervises TPC in advancing its disposal technologies to align with international standards, referencing guidelines such as the International Atomic Energy Agency's (IAEA) SSG-23.

The NSC requires TPC to submit an updated "Low-Level Radioactive Waste Disposal Technical Feasibility Assessment Report" every four years. This ensures that TPC's disposal technologies represent the best available practices, enhancing facility safety, and protecting public safety and environmental quality.

 The Contingency Project for the Disposal Plan

Final disposal facility site selection processes often face significant uncertainty, leading to delays or obstacles in planning progress. As a countermeasure, the international community has advocated for the establishment of the Central interim storage facilities to serve as temporary repositories for nuclear waste. Taiwan's Executive Yuan's the Task Force for the Promotion of a Nuclear-Free Homeland has mandated that TPC actively promote the construction of the Central interim storage facilities for radioactive waste and engage in public communication. TPC is also required to establish guidelines for site selection.

The Central Interim Storage facilities function as storage facilities in essence. The NSC's existing safety management regulations for storage facilities apply to the application and review process for such facilities. Additionally, the NSC has issued the "Site Selection Guidelines for Consolidated Radioactive Waste Storage Facilities", providing objective standards for the MOEA and TPC to follow during the site selection process.
 

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