UPSC MainsGEOLOGY-PAPER-II201920 Marks
Q33.

What are different types of radioactive waste forms? How are they disposed in geological repository?

How to Approach

This question requires a detailed understanding of radioactive waste management. The approach should involve first defining radioactive waste and categorizing its forms based on activity level and half-life. Then, the answer should focus on geological repositories, explaining the site selection criteria, engineering design, and long-term safety considerations. A structured response with clear headings and subheadings will be beneficial. Mentioning international examples will add value.

Model Answer

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Introduction

Radioactive waste is a byproduct of nuclear power generation, medical isotope production, research, and industrial applications. Its safe and secure management is crucial for protecting human health and the environment. This waste varies significantly in its radioactivity and longevity, necessitating different handling and disposal strategies. The most promising long-term solution for high-level radioactive waste is disposal in deep geological repositories, engineered barriers designed to isolate the waste from the biosphere for thousands of years. This answer will detail the different types of radioactive waste forms and the process of their disposal in geological repositories.

Types of Radioactive Waste Forms

Radioactive waste is broadly categorized based on its level of radioactivity and the duration of its hazardousness. The International Atomic Energy Agency (IAEA) classifies radioactive waste into the following categories:

  • Exempt Waste: Contains very low levels of radioactivity and does not require special regulatory control.
  • Very Low-Level Waste (VLLW): Contains low levels of radioactivity and can be disposed of with minimal isolation.
  • Low-Level Waste (LLW): Includes items like contaminated clothing, tools, and filters. It typically contains short-lived radionuclides and requires shallow land burial.
  • Intermediate-Level Waste (ILW): Contains higher levels of radioactivity than LLW and may require shielding during handling and transport. It includes resins, chemical sludge, and reactor components.
  • High-Level Waste (HLW): The most radioactive waste, primarily spent nuclear fuel and waste from reprocessing spent fuel. It generates significant heat and requires long-term isolation.

Waste Forms & Conditioning

Before disposal, radioactive waste is often conditioned into a stable form to minimize its mobility and enhance its safety. Common waste forms include:

  • Cementation: LLW and ILW are often mixed with cement to create a solid matrix.
  • Bituminization: Using bitumen (asphalt) to encapsulate waste, particularly ILW.
  • Vitrification: HLW is typically vitrified – incorporated into a glass matrix – to create a highly durable and leach-resistant waste form. This process significantly reduces the volume of the waste and immobilizes the radionuclides.
  • Ceramic Waste Forms: Research is ongoing into using ceramic materials as alternative waste forms for HLW, offering potentially superior durability.

Disposal in Geological Repositories

Deep geological repositories (DGRs) are considered the most viable long-term solution for HLW and some ILW. The concept involves isolating the waste deep underground in a stable geological formation.

Site Selection Criteria

Selecting a suitable site for a DGR is a complex process involving rigorous scientific investigation. Key criteria include:

  • Geological Stability: The site should be located in a geologically stable area with minimal seismic activity and volcanic risk.
  • Hydrogeology: Low groundwater flow rates and minimal permeability are essential to prevent radionuclide migration.
  • Rock Properties: The host rock should have good sorption properties to retard radionuclide transport. Suitable rock types include granite, clay, salt, and shale.
  • Depth: Repositories are typically located at depths of several hundred meters (e.g., 500-1000m) to provide sufficient shielding and isolation.
  • Distance from Population Centers: The site should be located in a sparsely populated area.

Engineering Design & Multi-Barrier System

A DGR employs a multi-barrier system to ensure long-term safety:

  • Waste Form: The vitrified waste itself is the first barrier.
  • Waste Canister: The waste is sealed in durable, corrosion-resistant canisters (e.g., made of stainless steel or copper).
  • Buffer/Backfill Material: The space between the canisters and the host rock is filled with a buffer material (e.g., bentonite clay) that swells when hydrated, sealing gaps and absorbing radionuclides.
  • Host Rock: The geological formation provides the final barrier, isolating the waste from the biosphere.

Operational Phases

The development of a DGR involves several phases:

  • Site Characterization: Extensive geological, hydrological, and geochemical investigations.
  • Repository Construction: Excavation of tunnels and chambers.
  • Waste Emplacement: Placing the waste canisters in the repository.
  • Repository Closure: Sealing the repository and monitoring its performance.
  • Post-Closure Monitoring: Long-term monitoring of the repository to ensure its continued safety.

International Examples

Several countries are actively pursuing DGR development:

  • Finland (Onkalo): The world’s first planned DGR for spent nuclear fuel, currently under construction.
  • Sweden (Forsmark): Approved a site for a DGR in 2022.
  • France (Cigéo): Developing a DGR in Bure, eastern France.
  • United States (Yucca Mountain): The Yucca Mountain project in Nevada faced significant political and public opposition and is currently stalled.

Conclusion

The safe disposal of radioactive waste is a critical challenge for nuclear energy-producing nations. Deep geological repositories, utilizing a multi-barrier system and carefully selected sites, represent the most promising long-term solution. While the development of DGRs is complex and faces public acceptance challenges, continued research, international collaboration, and transparent communication are essential to ensure the responsible management of this hazardous waste for generations to come. The success of projects like Onkalo in Finland will be crucial in demonstrating the feasibility and safety of this approach.

Answer Length

This is a comprehensive model answer for learning purposes and may exceed the word limit. In the exam, always adhere to the prescribed word count.

Additional Resources

Key Definitions

Radionuclide
An unstable atom that decays and emits radiation. Radionuclides are the source of radioactivity in radioactive waste.
Half-life
The time required for half of the radioactive atoms in a sample to decay. Radioactive waste contains isotopes with varying half-lives, ranging from seconds to millions of years.

Key Statistics

Globally, over 230 nuclear reactors generate approximately 10,000 tonnes of spent nuclear fuel annually (IAEA, 2023 - knowledge cutoff).

Source: International Atomic Energy Agency (IAEA)

As of 2021, approximately 30 countries operate commercial nuclear power plants, generating radioactive waste that requires long-term management (World Nuclear Association - knowledge cutoff).

Source: World Nuclear Association

Examples

The Swedish Spent Fuel Repository

Sweden's planned repository at Forsmark will utilize copper canisters to encapsulate spent nuclear fuel, surrounded by bentonite clay. This design aims to provide long-term isolation and prevent radionuclide leakage.

Frequently Asked Questions

What is the role of bentonite clay in a geological repository?

Bentonite clay swells when it comes into contact with water, creating a low-permeability barrier that seals gaps around waste canisters and absorbs radionuclides, hindering their migration.

Topics Covered

GeologyEnvironmental GeologyNuclear GeologyWaste ManagementGeological StorageSite Selection