Patent classifications
G21C19/02
Method for Efficient Power Plant Maintenance
Methods for nuclear power plant maintenance which reduces outage time while a polar crane is maintained. In some examples, the method includes the steps of placing an auxiliary crane on a set of rails of a polar crane, using the auxiliary crane to perform maintenance work while the polar crane is maintained, and removing the auxiliary crane after maintenance work on the polar crane is completed. In some further examples, the method includes placing a second auxiliary crane on the set of rails. Still in other example, bridge motors are used to turn the rails, allowing the auxiliary crane to reach every area of the plant floor.
Insitu Process and System for the Dry Sampling & Characterization of Irradiated Zircaloy Pressure Tubes, Activated Alloy Metals and Graphite from Nuclear Reactor Components
Disclosed is a process method and system for upfront sampling and characterization to selectively and representatively sample for activation levels of nuclear reactor core irradiated metal alloy internal components using a specialized robust hard metal reactor bit hollow tungsten carbide sampling head in conjunction with bespoke angled sampling gantry. The invention relates to the field of a nuclear reactor metal alloy vacuum hollow sampling head, sampling gantry, and retrieval system. The nuclear-activated metal alloys are drilled and sampled using a TruProBit® metal cutting drill bit. The long hollow drill bit with a hollow metal sampling head traverses the nuclear reactor metal layers and void spaces to cut and retrieve only metal alloy samples. The dry vacuumed airflow picks up the discrete incremental sample of metal filings, chips, and dust produced by the hollow metal cutting edges of the sampling head into a filter and then analyzed for radionuclides of concern.
Method for housing nuclear reactor modules
An in-core instrumentation system for a reactor module includes a plurality of in-core instruments connected to a containment vessel and a reactor pressure vessel at least partially located within the containment vessel. A reactor core is housed within a lower head that is removably attached to the reactor pressure vessel, and lower ends of the in-core instruments are located within the reactor core. The in-core instruments are configured such that the lower ends are concurrently removed from the reactor core as a result of removing the lower head from the reactor pressure vessel.
Method for housing nuclear reactor modules
An in-core instrumentation system for a reactor module includes a plurality of in-core instruments connected to a containment vessel and a reactor pressure vessel at least partially located within the containment vessel. A reactor core is housed within a lower head that is removably attached to the reactor pressure vessel, and lower ends of the in-core instruments are located within the reactor core. The in-core instruments are configured such that the lower ends are concurrently removed from the reactor core as a result of removing the lower head from the reactor pressure vessel.
Pellet handling apparatus and fuel rod loading method
A pellet magazine includes a plurality of pellet bores sized to receive pellets for loading into a fuel rod. A fuel rod loading system includes a plurality of pellet loading stations each designated to load a single pellet type into one or more pellet bores of the pellet magazine, a rod loading station configured to unload pellets from the pellet bores of the pellet magazine into a fuel rod, and a conveyance system configured to transport the pellet magazine to the loading stations and then to the rod loading station in a defined sequence.
Pellet handling apparatus and fuel rod loading method
A pellet magazine includes a plurality of pellet bores sized to receive pellets for loading into a fuel rod. A fuel rod loading system includes a plurality of pellet loading stations each designated to load a single pellet type into one or more pellet bores of the pellet magazine, a rod loading station configured to unload pellets from the pellet bores of the pellet magazine into a fuel rod, and a conveyance system configured to transport the pellet magazine to the loading stations and then to the rod loading station in a defined sequence.
Device for magnetically removing a capsule containing Co-60 from a burnable absorber rodlet
An apparatus for removing irradiated capsules containing produced Co-60 from a plurality of burnable absorber rodlets. The apparatus comprises a solenoid that induces an electromagnetic flux into a Co-60 capsule and magnetically locks the Co-60 capsule in parallel with the apparatus. The apparatus is slideable along a longitudinal axis of the burnable absorber rodlet and causes the Co-60 capsule to overcome holding forces exerted on it.
Quick-detachable connecting device with simplified thread structure and connection method using same
A quick-detachable connecting device with a simplified thread structure includes a top nozzle, a connecting tube sleeve, a locking tube and a locking piece. The top nozzle is provided with a through hole, in which the connecting tube sleeve is assembled. The locking tube is accommodated in the through hole. An outer peripheral surface of the locking tube is provided with a second stopping structure, and an inner peripheral surface of the connecting tube sleeve is provided with a first stopping structure fitting the second stopping structure. The locking piece is movably arranged on the locking tube for circumferentially limiting or releasing the locking tube. A connection method using such connecting device is also provided.
Quick-detachable connecting device with simplified thread structure and connection method using same
A quick-detachable connecting device with a simplified thread structure includes a top nozzle, a connecting tube sleeve, a locking tube and a locking piece. The top nozzle is provided with a through hole, in which the connecting tube sleeve is assembled. The locking tube is accommodated in the through hole. An outer peripheral surface of the locking tube is provided with a second stopping structure, and an inner peripheral surface of the connecting tube sleeve is provided with a first stopping structure fitting the second stopping structure. The locking piece is movably arranged on the locking tube for circumferentially limiting or releasing the locking tube. A connection method using such connecting device is also provided.
IN-CORE INSTRUMENTATION
An in-core instrumentation system for a reactor module includes a plurality of in-core instruments connected to a containment vessel and a reactor pressure vessel at least partially located within the containment vessel. A reactor core is housed within a lower head that is removably attached to the reactor pressure vessel, and lower ends of the in-core instruments are located within the reactor core. The in-core instruments are configured such that the lower ends are concurrently removed from the reactor core as a result of removing the lower head from the reactor pressure vessel.