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    • 1. 发明专利
    • AUTOMATICALLY CALIBRATING GAS FLOWMTER
    • JPH0599724A
    • 1993-04-23
    • JP26197891
    • 1991-10-09
    • MITSUBISHI HEAVY IND LTD
    • UEJIMA NAOYUKIKAWAMURA WATARUHATANO SHIGEKAZUNISHIHARA YUKIOSATO AKIO
    • G01F1/50G01F15/02G01F15/04
    • PURPOSE:To accurately measure the flow rate of a gas even when the composi tion of the gas changes during measurement by detecting the composition of the gas and correcting the measured flow rate value of the gas based on the composition detected result of the gas. CONSTITUTION:This gas flowmeter 3 measures the flow rate of a gas 2 to be measured and outputs an electric signal 9 to a second signal converter 8. An He concentration analyzer 5 measures the He concentration of the sample 10 of the gas 2 supplied through a bypass pipe 4 and outputs electric signals 11 and 12 to a first and the second signal converters 7 and 8. A mass flowmeter 6 supplies the sample 10 to the analyzer 5 by a fixed amount and outputs an electric signal 13 to the first signal converter 7 as the flow rate of the 10. The converter 7 accurately finds the actual flow rate of the sample 10 by performing arithmetic operation on the basis of the signals 12 and 13 and outputs an electric signal 14 to the flowmeter 6 so that the glow rate of the sample 10 can always become a set value. The second signal converter 8 can accurately find the actual flow rate of the gas 2 to be measured by performing arithmetic operation on the basis of the signals and 11.
    • 2. 发明专利
    • TREATMENT OF USED RADIOACTIVE ION EXCHANGE RESIN
    • JPH04102100A
    • 1992-04-03
    • JP21903190
    • 1990-08-22
    • MITSUBISHI HEAVY IND LTD
    • NISHIHARA YUKIOWAKUTA KUNIHARUKOHANAWA OSAMUINAGAKI YUZOMIYAMOTO HITOSHI
    • G21F9/30G21F9/04
    • PURPOSE:To effectively control the number of production of drum cans in accordance with a small capacity of a concentrated waste liquid storage tank by dividing elution operation into three stages in accordance with the radioactive concentration of waste resin or elution liquid. CONSTITUTION:Waste resin of an elution tank 1 is immersed in acid solution to elute radioactive materials which resin has. Next, the elution solution is supplied to the left chamber of a diffusion dialysis tank 2 and the acid solution of the elution solution is separated to recover into the right chamber thereof to reuse in the tank 1. The acid solution is almost recovered and waste liquid containing a large quantity of radioactive materials is drained from the upper part of the left chamber of the tank 2. After the waste liquid of high radioactive concentration produced during the initial stage of elution operation is supplied to a first neutralization tank 3 to neutralize with alkali solution, it is evaporated and concentrated in a concentrator 6. Since its concentration is high, it is stored in a first batch tank 7 during a long term to solidify after radioactivity attenuation. After the waste liquid during an intermediate term of operation is supplied to a second neutralization tank 4, neutralization, evaporation and concentration are performed to solidify after it is supplied to a second batch tank 8. After the waste liquid during the later term of the operation is supplied to a third neutralization tank 5, neutralization is performed to fully lower radioactivity concentration so as to drain into a liquid waste disposal system.
    • 6. 发明专利
    • Apparatus for dehumidifying solid adsorbent
    • 去除固体吸附剂的装置
    • JPS61120618A
    • 1986-06-07
    • JP24043084
    • 1984-11-16
    • Mitsubishi Heavy Ind Ltd
    • NISHIHARA YUKIOKOBANA KAZUHARUMINEMOTO MASAKIFUNAKOSHI TOSHIOUEJIMA NAOYUKI
    • B01D53/26B01D53/04G21F9/02
    • PURPOSE: To simplify a system by reducing the flow amount of regeneration gas and reducing the capacities of a rare gas hold-up apparatus and a dehumidification apparatus, by bringing a dehumidification tower to a direct heating system and returning gas after regeneration to the waste gas line of an apparatus inlet.
      CONSTITUTION: The waste gas 1 of an atomic power plant is passed through a cooler 2 and a dehumidifier 4 to preliminarily remove hygroscopic moisture and dehumidified in a dehumidication tower 8 to be sent to a rare gas hold-up apparatus 20. A dehumidification tower 12 is heated by a heater 9 to desorb adsorbed hygroscopic moisture and this desorbed hygroscopic moisture is exhausted by a small flow amount of regeneration gas 19 to be returned to the line of waste gas 1 of the apparatus inlet through a valve 17 and sent to the cooler 2 and the dehumidifier 4 along with the waste gas to preliminarily remove hygroscopic moisture while the dehumidified gas is further dehumidified by the dehumidification tower 8 to be sent to the rare gas hold-up apparatus 20. By this method, a regeneration gas cooler and the dehumidifier can be used in common in the waste gas side.
      COPYRIGHT: (C)1986,JPO&Japio
    • 目的:通过减少再生气体的流量和降低稀有气体滞留装置和除湿装置的容量来简化系统,通过将除湿塔排入直接加热系统并将再生后的废气再循环到废气中 设备入口线。 构成:原子能发电厂的废气1通过冷却器2和除湿器4,以预先除去吸湿水分并在除湿塔8中除湿,送到​​稀有气体保持装置20中。除湿塔12 被加热器9加热以解吸吸附的吸湿性水分,并且该解吸的吸湿水分被少量的再生气体19排出,以通过阀17返回到设备入口的废气1的管线并被送到冷却器 2和除湿器4连同废气一起预先除去吸湿水分,同时除湿气体通过除湿塔8进一步除湿,送到​​稀有气体保持装置20中。通过这种方法,再生气体冷却器和 除湿器可以在废气侧普遍使用。
    • 8. 发明专利
    • METHOD FOR SOLIDIFYING RADIOACTIVE SLUDGE BY WATER HEAT
    • JPH01184498A
    • 1989-07-24
    • JP758388
    • 1988-01-19
    • MITSUBISHI HEAVY IND LTD
    • NISHIHARA YUKIOTANII TADAAKIMIYAMOTO HITOSHI
    • G21F9/06G21F9/00G21F9/16
    • PURPOSE:To solidify radioactive sludge as a stable synthetic rock having a high volume reducing property by putting the radioactive sludge and the compressed filter body of the solidified substrate thereof into a container and solidifying the same in this state by water heat. CONSTITUTION:A mixture composed of the solidified substrate essentially consisting of SiO2 and an alkali additive is charged into a cylinder 2 corresponding to the solidifying container and is compressively molded under about 300kg/cm pressure to form a filter layer 9 having the molding thickness of about 1/10 the bore of the cylinder 2. The mixture 5 prepd. by mixing the pseudo radioactive sludge, the solidified substrate and the alkali additive at 3:0.8:0.2 ratio is charged onto the previously formed filter layer 9 in the cylinder 2 and is compressively filtered by the filter layer 9 under about 300kg/cm compression pressure. The filter water to be discharged from the lower part of the filter layer at this time is discharged through a discharge pipe 7 and a discharge valve 8 to the outside of the cylinder 2. Since the filter layer 9 consists of the solidified substrate and additive which are the same as the mixture 5 thereon, both the filter layer and the mixture are integrated by the solidification reaction.