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    • 9. 发明授权
    • Vibrating assembly for pressurized water reactor ice baskets
    • 压水堆冰篮振动组件
    • US5456532A
    • 1995-10-10
    • US235707
    • 1994-04-29
    • James PowersLydia Demski
    • James PowersLydia Demski
    • G21C9/012G21C19/00
    • G21C9/012G21Y2002/206G21Y2004/20Y02E30/32
    • A vibrating assembly for vibrating an ice basket of a pressurized water reactor comprises first and second vibrators and a bracket operatively connected to the vibrators. The bracket includes a horizontally extending first armature portion and a horizontally extending second armature portion pivotably attached to the second armature portion. The first and second armature portions have clamps extending downwardly from each of their ends, and each of the clamps includes an arcuate groove extending vertically upwardly from its bottom surface to engage the rim of the ice basket. An attachment portion extends vertically upwardly from and is formed unitarily with the first armature portion, the vibrators being attached to the sides of the attachment portion. The clamps extending from the second armature portion are pivotably connected to and are also laterally adjustable with respect to the first and second ends of the second armature portion.
    • 用于振动加压水反应堆的冰篮的振动组件包括第一和第二振动器和可操作地连接到振动器的支架。 支架包括水平延伸的第一电枢部分和可枢转地附接到第二电枢部分的水平延伸的第二电枢部分。 第一和第二衔铁部分具有从其每个端部向下延伸的夹具,并且每个夹具包括从其底表面垂直向上延伸以与冰篮的边缘接合的弓形凹槽。 附接部分从第一衔铁部分垂直向上延伸并且与第一电枢部分一体地形成,所述振动器附接到附接部分的侧面。 从第二衔铁部分延伸的夹具可枢转地连接到第二衔铁部分的第一和第二端并且也可相对于第二衔铁部分的第一和第二端侧向可调节。
    • 10. 发明授权
    • Passive heat removal from nuclear reactor containment
    • 从核反应堆容器中被动去除热
    • US5082619A
    • 1992-01-21
    • US432246
    • 1989-11-06
    • Craig D. Sawyer
    • Craig D. Sawyer
    • G21C9/004G21C9/012G21C15/18
    • G21C15/18G21C9/012G21Y2002/205G21Y2004/402Y02E30/40
    • A nuclear system of the type which includes a containment wherein a nuclear reactor pressure vessel is located has a suppression pool to which steam can be vented so that it will condense and reduce the pressure in the pressure vessel upon the happening of an accident such as loss of reactor coolant or a steam pipe failure. Steam also can be vented directly to the containment space to further reduce pressure in the reactor. When reactor pressure is lowered to a certain pressure value, a gravity supply of water from an elevated pool of water will have a sufficient head to flow against the pressure in the reactor and into the reactor to submerge the fuel rods in the reactor. One or more isolation condensers are submerged in a large supply of water this supply being elevated some distance above the pressure vessel. At least one isolation condenser has inlet thereto communicated to an open entry conduit disposed in the containment. Steam in the containment space can enter the isolation condenser to be cooled at any time an accident occurs and steam is vented into the containment. The condensing of steam in the condenser boils water in the large supply but since the large water supply is open to atmosphere the boil-off is vented. Condensate resulting from cooling occurring in the isolation condenser is returned to the suppression pool and non-condensable gases present in the steam being condensed are separated from the condensate and vented to the suppression pool.