Title :
Development of Thimble Handling System for Neutron Flux Mapping
Author :
Cho, Byung-Hak ; Byun, Seung-Hyun ; Park, Joon-Young ; Lee, Jae-Kyung
Author_Institution :
Power Generation Lab., KEPRI, Daejeon
Abstract :
The in-core neutron flux mapping system in a pressurized water reactor yields information on the neutron flux distribution in the reactor core at selected core locations by means of movable detectors. The obtained data are used to verify the reactor core design parameters. The detector cables run through guide tubes (thimbles), and typically thirty six to fifty thimbles are allocated in the reactor depending on the number of fuel assemblies. For reactor operation, the thimbles are inserted into nuclear fuel assemblies through conduits connected from the bottom of the reactor vessel to a seal table. During the plant refueling outage period, the thimbles are withdrawn up to 4 meters from the seal table, the height of fuel assemblies. Thimble handling work has been performed by maintenance personnel. Manual handling efficiency is low due to narrow and high-radiation working environment around the seal table. Besides, manual force exerted on the thimbles is not constant and usually does not have unique direction, which may cause serious damage to the thimbles. To overcome these difficulties, automatic handling system for in-core neutron flux mapping thimbles has been developed, and the validity of the developed system is shown via experiments
Keywords :
fission reactor core control; fission reactor design; fission reactor fuel; fission reactor safety; fission reactor theory; neutron flux; nuclear reactor maintenance; automatic handling system; conduits; guide tubes; high-radiation working environment; in-core neutron flux mapping system; maintenance personnel; manual force; manual handling efficiency; movable detector cables; nuclear fuel assemblies; plant refueling outage period; pressurized water reactor; reactor core design parameters; reactor operation; reactor vessel; safety equipment; seal table; thimble handling system; Assembly; Automatic control; Cables; Control systems; Detectors; Inductors; Neutrons; Nuclear fuels; Power generation; Seals; detector thimble; nuclear in-core flux mapping system; thimble handling system;
Conference_Titel :
SICE-ICASE, 2006. International Joint Conference
Conference_Location :
Busan
Print_ISBN :
89-950038-4-7
Electronic_ISBN :
89-950038-5-5
DOI :
10.1109/SICE.2006.315153