DE1101635B - Nuclear reactor pressure vessel - Google Patents

Description

GERMAN

The invention relates to a nuclear reactor pressure vessel with a coolant discharge line in the upper area of the pressure vessel, a pressure chamber that extends downward from a bottom opening of the container extends out and an open end in the pressure vessel and a coolant inlet conduit has, which leads to a chamber outside the pressure vessel, and with a grid base for the Reactor core in the pressure vessel.

When designing nuclear reactors of the gas-cooled thermal reactor type, which are operated by a pressure vessel are included, the problem arises of how to store the container and the weight of one massive or relatively heavy reactor core to be transferred through the container in such a way that impermissible Stresses and bending moments in the container are avoided. In addition, the under The reactor operating conditions take into account the high temperature fluctuations occurring throughout the vessel will.

A nuclear reactor pressure vessel with an associated bearing or support is already known, which has a tube opening into the upper part, in which a pressure chamber is located extends below out of an opening in the bottom of the pressure vessel, into which a tube opens. The container carry movable bearing columns that are spaced around the pressure chamber, with support brackets welded to the outside of the container, which rest on the pillars, and correspondingly arranged support brackets are provided on the inside of the container, which take the load of the reactor core. The load caused by the reactor core is thus over Transferred the container through the support brackets, which brings the risk of complicated or Unclear bending stresses occur in the pressure vessel with temperature fluctuations, in particular at the connection points between the support brackets and the container.

The purpose of the invention is to create a pressure vessel with an associated holder, which this Is exposed to danger to a far lesser extent.

In the case of the nuclear reactor pressure vessel mentioned at the outset, this is achieved in that according to the invention both the pressure vessel and the grid base for the reactor core rest on the pressure chamber. Through this the most stressed parts of the pressure vessel support are kept at a constant temperature held, namely on that of the coolant, which through the pipe into the support or carrying chamber enters or arrives.

In that, according to the invention, both the nuclear reactor pressure is retained

Applicant:

United Kingdom

Atomic Energy Authority,

London

Representative: Dipl.-Ing. E. Schubert, patent attorney,
Siegen, Oranienstr. 14th

Claimed priority:
Great Britain June 17, 1957

Jack Jones Griffiths,

Culcheth, Warrington, Lancashire (UK),
has been named as the inventor

Pressure vessels as well as the reactor core are supported solely on the pressure chamber, oppose known ones Embodiments have practically no intricate tensions. This reactor is as a result simple, lighter and cheaper to manufacture, and moreover, with greater security.

The invention is now to be described in more detail with reference to the drawing which shows it, for example, which represents a longitudinal section will be explained. As can be seen from the drawing, has a spherical Pressure vessel 1 outflow pipes 2 which open into the upper portion of the boiler 1, and is on a pressurized chamber 3, which extends downward from an opening in the bottom of the pressure vessel 1 extends out and is determined by a flange 4 which is part of the chamber 3, wherein the Flange 4 is welded to the pressure vessel 1 to support it. The chamber 3 has an open end5 in the pressure vessel 1 and a closed end 6 outside the pressure vessel 1. A reactor core holding grid 7 inside the pressure vessel 1 is held by the chamber 3 via a support structure 8, while the inlet pipes 9 are provided for connection to the chamber 3.

The pressure vessel 1 is provided with an inner lining layer 11 provided. The support structure has longitudinal plates 12 and transverse plates 13. That Grid 7 holds a reactor core, which consists of a

109 52Ϊ / 571

inner core 14 and an enclosing reflector zone 15 consists. Support members 10 are attached to the chamber 3 and welded to the base plate 16, the latter being mounted on the base 17. Bluff body or baffles 18 and 19 are provided to prevent the flow of coolant past the reactor core. Access pipes 20 running through the pressure vessel 1 are provided.

The coolant enters the chamber 3 from the inlet pipe 9 and flows through the open end 5 of the Chamber 3 in the reactor core to cool it, and then emptied from the pressure vessel 1 through the outflow pipes 2.

The chamber 3, the flange 4 and the lower part of the pressure vessel 1 can during operation of the reactor be kept at a constant temperature by taking the instep temperature of the coolant keeps constant. In this way, neither the flange 4 itself, while it is all the weight of the pressure vessel 1 holds and as a result heavily

is addressed, parts still connected with it are subject to additional stress due to temperature gradients granted.

Claims (1)

PATENT CLAIM! Nuclear reactor pressure vessel with a coolant discharge line in the upper area of the pressure vessel, a pressure chamber extending downwardly from a bottom opening of the container and has an open end in the pressure vessel and a coolant inlet conduit leading to a Chamber outside of the pressure vessel leads, and with a grid base for the reactor core inside Pressure vessel, characterized in that both the pressure vessel (1) and the grid base (7) for the reactor core rest on the pressure chamber (3). Considered publications:
Nucl. Engineering, 1, 1956/57, p. 269. 1 sheet of drawings ι 109 52Ϊ / 571 2.61