94 results about "Fuel cycle" patented technology

A head assembly for a reactor pressure vessel includes a removable closure head, an array of control rod drive mechanisms, a seismic support platform, a missile shield assembly and a cooling system for drawing atmospheric air across electromagnetic coil stack assemblies. The cooling system includes: a lower shroud surrounding the coil stack assemblies with an end open to the atmosphere around the CRDMs; a plurality of extending internal ducts disposed within the array of CRDMs upwardly to an upper plenum disposed above the seismic support platform and a plurality of fan assemblies disposed on the upper plenum. The missile shield is disposed within the upper plenum. The cooling system effectively cools the coil stack assemblies during fuel cycles and does not hinder access to the CRDMs during an outage. The head assembly has lift legs for transporting either the entire head assembly as an integral unit or the structure above the seismic support platform a subassembly.

The invention discloses a steam water heat recovery and fuel heating integrated efficiency-increasing system for a combined-cycle power plant. The steam water heat recovery and fuel heating integrated efficiency-increasing system comprises a gas turbine unit, a gas inlet pipeline, a feeding pipeline, a waste heat boiler, a chimney, a steam unit, a steam water heat recovery system and a fuel cycle preheating system. The gas inlet pipeline and the feeding pipeline are connected with the gas turbine unit. The waste heat boiler is connected with an outlet of the gas turbine unit. The chimney is connected with the waste heat boiler. The steam unit is connected with the waste heat boiler. The steam water heat recovery system is connected with a steam turbine. The fuel cycle preheating system is connected with the feeding pipeline and the waste heat boiler. By means of the steam water heat recovery and fuel heating integrated efficiency-increasing system for the combined-cycle power plant, the overall combined-cycle heat efficiency is improved, and cost is reduced.

The invention discloses a fuel oil system of a ship; the fuel oil system comprises a main engine, a low vulcanized oil cabin, a diesel oil cabin and a heavy oil cabin, wherein the main engine is connected with an oil supply unit by an oil line; the low vulcanized oil cabin, the diesel oil cabin and the heavy oil cabin are connected with the oil supply unit by an oil line; the oil supply unit comprises a low vulcanized oil cooler, an oil feed pump, a fuel oil heater, a fuel oil self-cleaning strainer, a fuel oil return cylinder and a fuel oil circulating pump; one end of the oil feed pump is connected with the fuel oil return cylinder; the other end of the oil feed pump is respectively connected with the low vulcanized oil cabin, the diesel oil cabin and the heavy oil cabin; a return circuit is arranged on the fuel oil return cylinder and is connected with the main engine; a return circuit is arranged on the fuel oil return cylinder and is sequentially connected with the fuel oil circulating pump, the fuel oil heater and the fuel oil self-cleaning strainer; the low vulcanized oil cooler is arranged between the fuel oil circulating pump and the fuel oil self-cleaning strainer; and necessary valves are arranged on the oil lines or pipelines. The low-sulfur fuel oil system of the ship of the invention has the advantages of being simple, free in oil line switching and stable in operating performances, meeting the requirements of various regulations and effectively reducing the operating cost; meanwhile, the service life of equipment is prolonged; and the fuel oil system has very good practical applicability and has very good economic benefits and social benefits.

A method for generating fuel loading data for a core in a nuclear reactor, wherein the core includes an array of fuel locations in the core, the method includes: defining an even cycle bundle shift map of fuel bundles to be shifted to another core location during an even fuel loading cycle; defining an odd cycle shift map of fuel bundles to be shifted to another core location during an odd loading cycle, wherein the odd cycle and even cycle are alternative and successive core refueling cycles; defining a discharge map identifying the another locations to receive the bundles from the locations identified in the even and odd cycle shift maps, and generating shuffling instructions indicating which fuel bundles from a prior fuel cycle are to be shifted to one of the another locations of the core for a subsequent fuel cycle, wherein bundles to be shifted during the even fuel loading cycle are selected from the fuel bundles to be shifted identified in the even cycle bundle shift map and bundles to be shifted during the odd fuel loading cycle are selected from the fuel bundles to be shifted identified in the odd cycle bundle shift map.

The invention relates to a sphere-bed high-temperature gas-cooled online refueling system, which belongs to the reactor engineering technology area. The states system includes four function subsystem that new fuel loading system, reactor core fuel cycle main system, spent fuel removing system, reactor core evacuation and re-loading system; which is composed of the charging hole (1), the cross ball counter (2), the isolation ball valve (3), the emptying chute (10), the dumping device (11), the broken spherical tank (12), the divider (40) and so on. The end of the charging hole (1) connects theacross ball counter (2), the end of the cross ball counter (2) connects the isolation ball valve (3),the end of isolation ball valve (3) connects the divider (40). The end of the divider (40) dividesinto two ways, each way connects a suit of the isolation ball valve (5). The invention saves the cost; guarantees the integrality of the fuel component in the entire reactor core loading process; canenhances the fuel simplification and the broken ball separation speed and the reliability, saves the cabin space; effectively control the transportation of the fuel element in system pipeline.

The invention discloses a calculation method used for searching for a balanced cycle of a fast neutron reactor. The method comprises the steps of 1, representing a fuel management scheme as multiple fuel management paths; 2, making a fuel cycle process equivalent to an approximate balanced cycle; 3, for the approximate balanced cycle, performing neutron transport and burnup coupling calculation of an in-reactor cycle to obtain a transmutation matrix of each stage of each fuel management path; 4, repeating the steps 2 and 3 until a nuclear density vector of each stage of each fuel management path is converged, thereby obtaining an in-reactor cycle mode; 5, performing linear interpolation or extrapolation on cycle length, and performing a search to obtain the in-reactor cycle mode meeting discharge burnup level requirements; 6, calculating spent fuel reprocessing recovery and new fuel reproducing processes, performing burnup calculation of the in-reactor cycle on a nuclear density vector of newly loaded fuel according to the transmutation matrix, and repeating the processes until the nuclear density vector of the newly loaded fuel of each fuel management path is converged; and 7, adjusting the enrichment degree of the newly loaded fuel to realize a target effective multiplication factor of a specified time point.