Specific Isotope Recovery TRIZ Cases

Curved-field velocity filtering separates Lu-177 from similar isotopes with high purity and controlled collection rates for scalable production.

A backward electron beam and removable charge rod improve ionization efficiency while enabling continuous ion source operation.

A carbon fiber lattice decelerates and captures accelerated ions to reduce sputtering and leave a high-isotope residue for extraction.

A carbon fiber lattice decelerates and captures high-energy ions through multiple deflections, reducing sputtering and yielding concentrated isotope residue.

A fibrous carbon lattice decelerates and retains ytterbium-176 ions, reducing sputtering and yielding a concentrated isotope residue.

A curved bremsstrahlung converter spreads focused electron-beam heat more evenly, enabling simpler cooling and longer converter life.

Selective thorium precipitation before chromatography isolates actinium and radium with less co-precipitation and smaller separation volumes.

Activated charcoal in a cylindrical mesh speeds 99mTc recovery from low-specific-activity 99Mo while alumina purification removes impurities.

Selective ion exchange and oxalic acid precipitation recover high-purity thorium and uranium from spent nuclear fuel with lower thorium loss.

A split alumina and metal-molybdate column limits Mo-99 breakthrough while improving Tc-99m elution and reducing generator size and weight.

Cyclotron-made copper-64 is purified from nickel and metal impurities using extraction and ion exchange chromatography for scalable PET isotope supply.

Bremsstrahlung irradiation and single-column chromatographic separation cut radionuclide isolation time while preserving high purity and yield.

Reducing UF6 to precipitated UF5 separates uranium from MoF6 efficiently, cutting acidic radioactive waste and aiding isotope recovery.

Phosphate-modified titania selectively captures 229Th to generate Ac-225 with high recovery and minimal isotope contamination.

Rapid SPS flash sintering cuts target holding time, lowers UAl2 content, and supports higher uranium loading with less scrap.

Segmented annular target plates on a rigid spine enable fast post-irradiation debundling, cutting handling time while preserving Mo-99 material integrity.

Computer-guided setup, purging, and quality control automate Rb-82 infusion while reducing staff radiation exposure and manual handling.

Np or Am microsphere targets enable Pu-238 production in commercial reactors while reducing contamination, material loss, and waste.

Stacked target plates with extractable central members speed Mo-99 production and disassembly for rapid titanium-molybdate-99 processing.

A split crucible and cooling plate assembly improves access and alignment to collect Lu-177 with minimal rare earth material loss.

Remote loading, orthogonal irradiation, and fluid cooling reduce operator exposure while improving radioisotope target handling and output.

Tandem DGA and HDAP columns speed Ac-225 purification from Ra, Pb, Po, Bi, and La, enabling high purity with direct eluate transfer.

Low-energy proton bombardment and staged chromatography produce high-specific-activity copper-64 with high purity for broader PET dosing.

HNO3 dissolution, water distillation, and cooling recover Ra-226 targets for reuse while limiting co-precipitation of Ac-225 and impurities.

A lithium-6 and deuterium converter around radium-226 turns thermal neutrons into fast neutrons to raise actinium-225 yield in reactors.

Continuous inert-gas sparging removes dissolved fission products from molten fuel salt, helping recover molybdenum-99 and sustain reactor efficiency.

A single-chamber diffusion generator keeps the precursor source off collection walls, producing high-purity 212Pb for safer transport.

A closely spaced converter, collimator, and target concentrates gamma beams for medical isotopes while reducing beam power and target material.

Porous or granular targets enable liquid elution of irradiated radionuclides with less process complexity and radioactive waste.

Phase transfer agents move molybdate into an organic phase, shortening Mo-99 purification and limiting decay loss.

An annular-plate target and gripper-twister tool speed irradiated plate disassembly for timely titanium-molybdate-99 processing.

Chemically inert 3D-printed scaffolds capture radionuclides while limiting radiolytic degradation and high-energy contaminants.

Inert-gas sparging removes dissolved fission products from molten fuel salt during full-power operation, reducing buildup and preserving reactor efficiency.

Segmented plates and a removable spine speed post-irradiation handling, addressing Mo-99's short half-life.

An automated handling unit keeps irradiated target containers sealed during transfer, then opens them for acid dissolution to limit operator radiation exposure.

An emanation box uses inert carrier gas to move Rn-220 into decay targets, reducing chemical separation and replenishment during Pb-212 production.

A single-chamber assembly lets 220Rn, 216Po, and 212Pb settle on container walls for high-purity production without processing.