Lesson 5 5.4 The PUREX Reprocessing Process

The fuel (whether from stripped Magnox or leached oxide) is dissolved in concentrated nitric acid. The uranium is oxidised to the 6+ valence state and nitrogen oxide gases are released:

3UO2+8HNO33UO2(NO3)2+2NO+4H2O3 \text{UO}_2 + 8 \text{HNO}_3 \rightarrow 3 \text{UO}_2(\text{NO}_3)_2 + 2 \text{NO} \uparrow + 4 \text{H}_2\text{O}

UO2+4HNO3UO2(NO3)2+2NO2+2H2O\text{UO}_2 + 4 \text{HNO}_3 \rightarrow \text{UO}_2(\text{NO}_3)_2 + 2 \text{NO}_2 \uparrow + 2 \text{H}_2\text{O}

Insoluble fission products (noble metals such as molybdenum, technetium, rhodium, and palladium, plus fine particles of stainless steel or Zircaloy) are removed by centrifuging.

Dissolver off-gases must be treated. Volatile fission products released during dissolution include:

  • Tritium (H-3)
  • Carbon-14 (as CO and CO₂)
  • Krypton-85
  • Iodine-129
  • Xenon

These gases are scrubbed with nitric acid (to remove NOₓ), sparged with air (to remove iodine), and scrubbed with caustic soda (to remove carbon-14). The nitrogen oxides can be treated and recycled as nitric acid.

Key Point: Care must be taken to ensure criticality safety during dissolution, especially when using enriched fuel. Favourable geometry vessels and gadolinium neutron poison are used as criticality controls.