Developing a new target design for producing ⁹⁹Mo in a MTR reactor.

Area of Science:

• Nuclear Engineering
• Radiochemistry
• Materials Science

Background:

• Molybdenum-99 (99Mo) is a critical radioisotope primarily produced via uranium fission in nuclear reactors.
• Current production methods in Material Testing Reactors (MTRs) face challenges in efficiency and waste management.
• Optimizing target geometry and in-core placement is crucial for improving 99Mo production.

Purpose of the Study:

• To investigate improvements in target geometry and in-core location for more efficient 99Mo production in MTRs.
• To parametrically assess target characteristics including geometry, location, material, density, and power density.
• To evaluate the usability of a new target design in the Tehran Research Reactor (TRR).

Main Methods:

• Utilized the stochastic code MCNPX 2.6.0 for neutronic analysis.
• Employed the computational fluid dynamics (CFD) code ANSYS for thermal-hydraulic analysis.
• Conducted a parametric investigation of target properties and in-core placement.

Main Results:

• A plate-type target design was identified as the most favorable.
• The proposed design meets safety criteria, enhances 99Mo production yield, and considers chemical processing and waste reduction.
• Neutronic and thermal-hydraulic analyses confirmed the design's viability for the Tehran Research Reactor (TRR).

Conclusions:

• The new plate-type target design significantly increases 99Mo production efficiency.
• The optimized design requires less initial material, leading to reduced nuclear waste and simplified processing.
• The research demonstrates a viable pathway to enhance 99Mo production without compromising reactor safety.