Fuel Elements TRIZ Cases

Positive-kick HiPIMS deposits metal-ceramic nanolayers on fuel cladding to resist oxidation, delamination, and fracture under reactor extremes.

HiPIMS with Positive Kick controls ion flux to deposit nanolayer coatings that improve ATF fuel cladding oxidation and thermal shock resistance.

Equal-area annular faces, a curved undercut, and DC resistance pressure welding improve fuel rod end plug bond quality and seal reliability.

Localized brazing closes a silicon carbide container while keeping the cavity below the enclosed object's degradation temperature.

Localized brazing seals a silicon carbide container while keeping the enclosed object below its degradation temperature.

An elastic insertion rod supports inner-pipe swaging to bond dissimilar metal cladding layers tightly without fillers, oxidation risk, or pipe damage.

A lever-and-wedge fastening mechanism locks nuclear fuel assemblies by static pressure, avoiding spring embrittlement and friction-based wear.

A columnar fuel module embeds sealed fuel cavities beside cooling through-holes to improve heat transfer, pressure resistance, and reactor safety.

Multi-lobed metal fuel elements increase heat-transfer area and self-spacing, enabling higher fissile loading with lower operating temperature.

Shorter wire-wrap pitch on outer fuel pins raises edge subchannel pressure drop, reducing temperature gradients and increasing reactor outlet temperature.

Dry pelletization and thermal processing form dense uranium fuel kernels for TRISO particles while avoiding liquid-process safety and logistics burdens.

A sliding end-cap fuel sleeve enables automated insertion and removal of TRISO compacts, cutting loading time and stuck-core risk.

Multiple corium containment layers and water cooling improve confinement reliability and promote solidification during severe reactor accidents.

A double shielding layer lets high-uranium-density fuel cut pellet temperature gradients while resisting water and vapor oxidation in water-cooled reactors.

Alternating annular fuel and heat conductive layers lets reactor core thermal output be tuned during design while reducing core temperature differences.

A graphite support with removable BeO inclusions boosts neutron reflection while cutting reflector mass and assembly effort in compact reactors.

A polycarbosilane and glass powder filler forms a dense SiC cladding joint that limits shrinkage and pores while improving hermeticity.

Conductive coatings bonded between dissimilar nuclear fuel layers improve heat transfer while avoiding molybdenum insert absorption and assembly cost.

Argon heating, cold pressing, and sintering of U-Mo powder improve molybdenum uniformity, pellet density, and reactor heat removal.

A multilayer chromium and zirconium or titanium alloy coating helps fuel assemblies resist steam oxidation, water corrosion, and chromium elution.

Most reflector mass is moved outside the vessel, shrinking molten salt reactor size while supporting neutronics and heat removal.

Spark plasma sintering densifies UO2 pellets with SiC or diamond to cut porosity, improve heat conduction, and reduce fuel cracking risk.

A conductive winding and compression pistons rapidly heat tubular nuclear fuel cladding while measuring mechanical behavior under accident conditions.

Layered additive manufacturing uses TPMS channels to maintain consistent enrichment across nuclear fuel segments and the reactor core.

Additive manufacturing divides nuclear fuel assemblies into segments, addressing fretting and debris while supporting higher burnup and longer life cycles.

Depositing a thermally conductive coating, then stacking and bonding fuel layers, addresses molybdenum-related neutron absorption and manufacturing complexity.

Factory-fabricated reactor modules address tight-tolerance construction by enabling separate shipment and on-site assembly within commercial transport limits.

Neutron shielding limits long-term damage to in-core electronics, helping stabilize sensor performance during reactor testing and operation.

An external proton beam drives (p,n) reactions in thorium molten salt, creating fission heat for power without heavy-metal targets.

Branch piping, free ball bearings, and coolant purification simplify shared steam generation while managing thermal expansion.

Segmented fuel rods manage linear heat rates during accidental control rod withdrawal by absorbing excess neutrons.

Segmenting fissile material into micrometer-scale structures dispersed in a matrix enables efficient post-irradiation separation of fission products.

Direct current sintering replaces slow thermal methods to rapidly fabricate gas-impermeable SiC matrix TRISO fuel pebbles with enhanced structural integrity.

A macrostructured composite fuel plate uses a honeycomb network of cavities to house nuclear fuel pellets within an inert matrix.

Inlet pipes form local sub-pressure zones that capture small debris particles, preventing damage to fuel assemblies and reducing replacement needs.

Interconnected voids in a nuclear fuel foam enclosure absorb thermal expansion, reducing pressure on structural walls and preventing pellet cracking.

Shadow analysis of aligned nuclear fuel pellets detects chamfer defects without complex illumination, improving inspection throughput.

A molten salt reactor cooling system manages temperature and pressure at the fuel salt gas interface to prevent noble gas bubble formation.

Rotating support portion maintains constant speed to deposit oxidation-resistant coating on cladding tubes.

Reduced-diameter cladding seat on end plugs controls sliding distance during resistance welding, enabling non-destructive examination of weld bonds.