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    • 3. 发明专利
    • REMOVAL OF CARBON ISOTOPE IN CONDENSED WASTE LIQUID
    • JPH0495800A
    • 1992-03-27
    • JP20752290
    • 1990-08-07
    • TOSHIBA CORP
    • SAKURAI MANABUHIRAYAMA FUMIOKUROSAWA SETSUMIKAMATA TOSHIMASA
    • G21F9/08
    • PURPOSE:To transport carbon isotopes such as C contained in condensed waste liquid, into vapour of pure water and decrease the density of the carbon isotopes in the condensed waste liquid by providing pure water into condensed waste liquid and processing it with evaporation condensation. CONSTITUTION:Provided with a waste liquid condenser are an evaporation condenser 2 to heat and evaporate the containing liquid and to produce condensed liquid 1, a steam condenser 4 to condense the vapour exhausted from the evaporation condenser 2 by cooling and to recover as condensed water 3, and a supply water tank 7 to store pure water 6 to supply to the evaporation condenser 2 via a water supply pump 5 etc. Condensed waste liquid 1 is produced by processing radioactive waste liquid containing a carbon isotope with mass number 14 by evaporation condensing, and then the evaporation condensation processing is continued by supplying pure water 6 to the condensed waste liquid 1. By this, C contained in the condensed waste liquid 1 is efficiently removed even in the conditions in the can of condenser 2 set on alkalic side.
    • 5. 发明专利
    • METHOD AND APPARATUS FOR NONDESTRUCTIVE ANALYSIS OF IODINE
    • JPH0875681A
    • 1996-03-22
    • JP21475594
    • 1994-09-08
    • TOSHIBA CORP
    • TAMURA TOSHIYUKIIGARASHI NOBORUHIRAYAMA FUMIO
    • G01N23/222
    • PURPOSE: To provide a device, which can be conveyed and set into an iodine adsorbing device that cannot be moved, can discriminate other components of radioactive product that coexists with the iodine and has a high analysis accuracy. CONSTITUTION: A material under inspection 1 is arranged in front of a neutron irradiating mechanism 2, and the neutrons are irradiated for the specified time. Then, the material under inspection 1 is moved to front part of a gamma-ray detecting mechanism 3 with a moving mechanism for the material under inspection. The gamma rays emitted from the material under inspection are detected and measured with a gamma-ray detector 10. The time from the end of the irradiation of the neutrons to the start of the detection of the gamma rays is set at the constant time including the moving time. Basically, cooling is performed for 10 minutes, and the attenuation for 2.4 minutes is allowed for the case of Ag-108. The gamma ray of 536KeV discharged from I-130m having the half-life of 9.16 minutes are noted, and the spectrometry measurement of the gammarays is performed.
    • 6. 发明专利
    • UTILIZING SPENT ION EXCHANGER RESIN
    • JPH04216498A
    • 1992-08-06
    • JP40323590
    • 1990-12-18
    • TOSHIBA CORP
    • SAKURAI MANABUHIRAYAMA FUMIOKUROSAWA SETSUMIKAMATA TOSHIMASA
    • G21F9/12
    • PURPOSE:To provide a usage of spent ion exchanger resin generated from a purification processing system in reducing the load of radioactive waste processing system by using the resin for processing waste liquid in processing equipment in a waste system. CONSTITUTION:In utilizing spent ion exchanger resin generated from a purification processing system which is not yet broke down the capacity of ion exchanger for a radioactive waste processing equipment by mixing and stiring waste liquid and the spent ion exchanger resin, electric conductivity degradation is prevented and bacteria and oil are eliminated. First, the spent ion exchanger resin is accepted in an inverse wash tank 2, and the condensate in a condenser 8 which is a high electric conductivity waste liquid abundant in bacteria and oil is sent to the inverse wash tank 2 through a condensate return pipe 13 and they are stired in the siring line 15 of the inverse wash tank to eliminate ion components, bacteria and oil. Then, they are sent to a deposition separation tank 3 to process by separation.