A cured polymer resin layer seals the top of radioactive waste in high-integrity containers to limit leakage after drops or cover damage.
A parallel path between the core inlet plenum and low-temperature pool cuts flow resistance and boosts natural circulation during reactor power outages.
A reactor-specific fuel assembly layout sets fuel rod and thimble positions to improve neutron leakage, reactivity, and power distribution.
A differential shielding mechanism prevents accidental core cutting from vessel motion and improves core column formation in mixed lithology.
Internal locking teeth grip the sleeve wall to pull damaged fuel or cluster rods after end-plug loss, preventing disengagement during extraction.
Distillation concentrates dilute radionuclides from sodium coolant, cutting background scatter and enabling near-real-time failed fuel pin detection.
An FCNN surrogate replaces RELAP5 and PSO rapidly screens nuclear accident sequences, cutting analysis time while preserving screening accuracy.
A negative deuterium ion source and lithium target generate neutron flux for compact, reliable 225Ac production with minimal back-streaming electrons.
A sealed vapor space and thermosiphon loop remove spent fuel pool heat by natural circulation and vapor condensation without pumps or external power.
A modular incore drive cable swaps neutron detectors and irradiation targets to measure core power distribution and produce radioisotopes without separate hardware.
Multiple neutron counting channels with different sensitivities improve BNCT dose measurement and support real-time irradiation adjustment.
A single underwater optical fiber emits light from its tip and side surface, expanding communication coverage without added circuit complexity.
Cryogenic granulation, freeze-drying, and calcination produce homogeneous actinide oxide powders with fewer fines and better flow for nuclear fuel fabrication.
Real-time neutron dose monitoring and correction help keep irradiation on target, reduce operator error, and protect normal tissues.
Cryogenic granulation, freeze-drying, and calcination produce homogeneous actinide oxide powders while reducing fine particle dispersal and filter clogging.
Concentric mirror and tandem coils create a concave field that cuts charged particle loss and improves plasma stability for fusion confinement.
A spacer on the thermal sleeve maintains clearance to the guide tube, preventing penetration wear while preserving coolant flow and retrofit ease.
Independent inner and outer plasma channels create layered flow for better Z-pinch stability, plasma control, and compact high-power output.
Electromagnetic irradiation drives phonon vibrations in host materials to screen Coulomb repulsion and raise fusion heat generation at lower temperatures.
A movable insulating insert changes discharge volume and flow mode to stabilize Z-pinch plasma and extend plasma lifetime.
Multiple flow, pressure, differential pressure, temperature, and humidity inputs are combined to calculate containment vessel leakage more accurately.
A rotating semi-annular SPMT and jack system removes tokamak vacuum vessel sections with less manual handling, damage risk, and downtime.
Liquid nitrogen cooling in a double containment structure limits reactor overpressure, rapid overheating, and radioactive leakage.
A submerged telescoping mast and self-leveling articulator position reactor tools without overhead support, freeing above-core space for refueling.
Using the lower penetration left by in-core instrument removal, this case enables concrete decontamination and waste removal while containing radioactive dust.