摘要:
The invention relates to a gas cooled high temperature reactor located in the cavity of a pressure vessel, with spherical fuel elements, and removal apparatus for fuel elements. The latter is made of at least one ceramic pebble outlet tube extending through the graphite structural parts of the nuclear reactor (bottom reflector, bottom layers) and a number of metal pebble outlet tubes installed through the bottom of the pressure vessel. They are arranged coaxially in the liner of the passage through the vessel. To be able to dismantle the metal pebble outlet tubes, they are constructed of several releasably interconnected tube segments. Between the uppermost tube segment and the corresponding ceramic pebble outlet tube a compensating tube is provided and connected with the tube segment by means of a sliding joint. The other end of the compensating tube is fastened to the thermal bottom shield. Relative movements caused by the thermal expansion of the bottom shield and the pebble outlet tubes are compensated by the slide joints. Simultaneously, the necessary tight sealing is assured.
摘要:
Disclosed is an angled gas conduit for a gas flowing under high pressure and at an elevated temperature which comprises a first conduit part and second conduit part connected at an angle forming an area of deflection for gas flowing within said conduit parts, an apertured plate arranged at an oblique angle within said conduit in the area of deflection, the apertured plate having a plurality of circular passages for directing the flow of gas in the conduit. A mounting arrangement for the apertured plate is also disclosed.
摘要:
A gas-cooled high temperature reactor is equipped with a supporting structure for the reactor core having a gas conduit passing through the support structure from a hot gas collecting space beneath the supporting structure. The supporting structure itself rests on a floor plate in a columnar arrangement. The floor plate also rests on support columns and possesses a disk-like center portion indirectly supporting the reactor core and an outer annular portion supporting a lateral thermal shield around the reactor core.
摘要:
A support structure for a nuclear reactor is disclosed comprising a primary support element connected with the roof of the pressure vessel and a secondary support element joined with the primary support element. The thermal roof shield and the roof reflector are connected to the secondary support element.
摘要:
A gas cooled, high temperature nuclear reactor is provided with a base plate arranged under the reactor core and over the bottom of the prestressed concrete pressure vessel serving as the bottom shield. The bottom shield comprises at least two plates arranged coaxially with respect to each other, one above the other. Each plate comprises several partially interconnected parts with the lower plate being placed at an axial and vertical distance from the bottom liner of the prestressed concrete pressure vessel and also from the upper plate.
摘要:
An improved design for shielding the component parts of a gas turbine power plant from radiation in a gas transport conduit is disclosed. The radiation shield and shielded gas conduit utilize a shielding arrangement comprising a displacement body arranged centrally within the conduit and a shielding annulus surrounding the displacement body. A shielding device provides for a first annular flow path for reactor cooling gas between the displacement body and shielding annulus and a second annular flow path for reactor cooling gas between the shielding annulus and the conduit housing. The shielding device provides protection against radiation without significantly disrupting the flow of the cooling gas in the conduits.
摘要:
The invention concerns a steam generator heated by the cooling gas of a nuclear reactor and arranged in the reactor pressure vessel within a vertical shaft. A blower associated with the steam generator is installed above it. The hot gas is conducted to the steam generator in the form of a helical bundle in the downward direction, with the hot gas being conducted initially downward through an annular channel and entering the bundle of heat exchanger tubes at a uniform velocity. The annular channel is sealed in upward direction by means of a sliding seal, which also serves as an earthquake support. In order to provide access to the feed water and live steam lines in view of the blower arranged on top, the two lines are conducted laterally out of and through the reactor pressure vessel. By means of the special fixation of the individual tubes of the heat exchanger bundle in vertical plates and the presence of an expansion zone for the recycling pipes, differential thermal expansion may be kept small.
摘要:
An inspection device for the inspection of internal spaces in nuclear reactor installations requires extremely small dimensions while being capable of use at high temperatures and exposures to radiation during shutdown periods of the reactor. The device is designed so that it is readily adapted to a particular inspection purpose. The particular device meeting these requirements comprises a camera arranged in a tube and cooled in such tube. The objective of the camera and/or a mirror are each connected with means for relative movement. A source light and the movement means are designed as separate structural elements which may be assembled in different combinations in a modular fashion.
摘要:
A plurality of graphite blocks forms a side reflector with an area of each block that allows a certain amount of radiation induced wear in a predefined zone facing the core of the reactor and an area separate from the wear zone for carrying the load bearing function of the side reflector. Most critical is the area of the upper range of the reactor core where radiation induced wear is greatest. The wear is taken into consideration in the design layout of the side reflector in the form of an increment to the thickness of the wall. The load bearing areas of each block provide the load bearing area for the entire side reflector. The side reflector is particularly suitable for high temperature gas-cooled reactors of the pebble bed type.
摘要:
A process is provided for the long term shutdown of a high temperature nuclear reactor comprised of a pile of spherical fuel elements in a core by means of a neutron absorbing absorber material wherein the absorber material consisting of spherical absorber elements is introduced in the core of spherical fuel elements in the form of a column, but wherein the intermixing of the absorber material with the fuel elements is prevented. An apparatus for practicing the process is also provided comprised of a graphite side reflector concentrically surrounding a circular cylindrical core filled with a pile of spherical fuel elements of a high temperature nuclear reactor, into which at least two nose shaped projections distributed uniformly about the circumference radially project, with each of the projections comprising a vertical cavity to contain the absorber material. The vertical cavity is located in the vicinity of the core in the area of the frontal side facing the core of each projection. Pourable absorber material provided by means of a reservoir located above the core and introduced into the vertical cavity penetrates the pile of spherical fuel elements in the form of a column, thereby absorbing neutron radiation.