GOVERNMENT RIGHTS

The invention described herein arose in the course of, or under, contract number DE-AT03-76SF71032 between the United States Department of Energy and the General Electric Corporation.

BACKGROUND OF THE INVENTION

1. Field of the Invention

This invention relates to nuclear reactors and protection of the public and, particularly, nuclear reactor containment structures which dissipate heat following an extremely low probability core meltdown and subsequent breach in the reactor vessel.

2. Background Discussion

Because of the radioactive materials contained in a nuclear reactor, great caution must be taken to prevent the escape of such materials to the environment. One type of nuclear reactor is the liquid metal fast-breeder reactor which employs a core immersed in liquid sodium coolant. If all heat removal capacity were lost, and temperatures within the reactor should exceed the melting point of the core, the core would disintegrate and core materials could reach the bottom of the reactor, where the debris layer heat generation rate could be sufficiently high to cause failure of the walls of the reactor vessel and guard vessel.

If this would occur both sodium and fragmented radioactive core debris would escape from the reactor vessel. The reactor containment must be designed to retain such radioactive materials which might penetrate the reactor vessel, and must prevent their entry into the environment where they can endanger public health and safety.

There is disclosed in U.S. patent application Ser. No. 800,566, filed Nov. 21, 1985 in the name of A. Hunsbedt, and J. D. Lazarus and entitled Heat Dissipating Nuclear Reactor, a novel reactor (herein referred to as Reactor I). This application disclosing Reactor I is incorporated herein by reference. The present invention provides an improvement in Reactor I.

BRIEF DESCRIPTION OF THE INVENTION

This improved version of Reactor I provides a reactor vessel disposed in a cavity lodged partly or completely below the surface of the earth, wherein the improvement is the use of a thick cast steel containment cavity surrounding the reactor vessel which cavity conforms closely in shape to the exterior of the reactor vessel and eliminates the guard vessel. This cast steel containment cavity has a thick steel base plate. In contrast to the Reactor I, wherein the containment cavity does not conform to the shape of the reactor vessel, the cast steel cavity described herein eliminates the mismatch between the round-bottomed reactor vessel and the flat-bottomed cavity. It fills in most of the void space between these two members with solid metal. In accordance with this invention, the debris is simply captured by the contoured containment cavity when there is a breach in the reactor vessel. The use of contoured cast steel containment greatly reduces the fall in sodium level occuring when sodium drains out of a breached reactor vessel. It provides a more coolable, safer reactor vessel.

Like the Reactor I, the improved reactor of this invention also has a hot zone beneath the basemat with means for introducing water and allowing steam formed to escape to the atmosphere. A plurality of metal pilings extend downwardly and outwardly into the earth from the basemat, supporting the reactor and serving as heat dissipating means.

BRIEF DESCRIPTION OF THE DRAWING

The FIGURE schematically illustrates the nuclear reactor containment of this invention, which is shown in crosssection with the reactor vessel breached and the radioactive core debris and liquid metal coolant being retained by the cast steel containment cavity.

DETAILED DESCRIPTION OF THE DRAWING

Referring to the FIGURE there is shown the nuclear reactor 10 of this invention disposed in a cavity 12 formed by excavating the earth. The reactor vessel 14 is generally cylindrical, but has a rounded bottom 16. The reactor vessel 14 is seated in a cast steel member 18 which has a interior contour 20 that conforms closely in shape to the exterior of the reactor vessel 14. This cast steel member 18 includes a thick, cylindrical sidewall 22 and a thick basemat 24 with flange members extending radially outwardly beyond the perimeter of the side wall. The sidewall thickness is nominally 8 inches and the basemat thickness is nominally 3 feet.

Like Reactor I, the reactor 10 of this invention has its top surrounded by a slab of concrete 25. The cavity wall is enwrapped by thermal insulation or a cooling jacket 26 and beyond this cooling jacket is biological shielding 28 such as concrete. The insulation or cooling jacket 26 prevents the shielding 28 and adjacent concrete structure from overheating. Like Reactor I there are a plurality of metal pilings 30 extending downwardly and outwardly into the earth. These pilings 30 are preferable in the form of H-Beams which are in intimate thermal contact with the basemat 24. The entire reactor 10 rests on a bed 32 of porous material and is essentially the same as the bed employed in Reactor I. There are two series of pipes 34 and 36 extending through it. The upper series of pipes serve as the steam vents and the lower series of pipes provide water to flood the bed 32. The water absorbs the heat in boiling, and carries it away via the steam which is vented by the second series of pipes to the atmosphere.

The principal advantage of this invention is that the guard vessel and reactor cavity are combined to provide a more compact and safer structure which holds the sodium 38 and core debris 40 as illustrated within the reactor 10 if the core melts and the reactor vessel subsequently breaches. This invention will improve the cooling of core debris when there is an overheating condition which the cooling means of this invention minimizes. As shown, there is a breach 42 in the reactor vessel 14 and the core debris 40 collects on the bottom of the cast steel member 18. The gap 44 between the reactor vessel 14 and the cast steel containment member 18 is of relatively small volume. If the reactor vessel is breached by a melted core, the resulting loss of liquid metal coolant from the reactor into this gap will result in only a small drop in sodium level. Reactor heat removal under these circumstances is via conduction down the pilings and steam generation, but may also be accomplished by the normal heat transfer members if they are operational; since the sodium level does not drop substantially as a result of reactor vessel breach, the normal heat exchangers and coolant circulation apparatus may still be submerged in sodium and may still be able to assist in cooling the melted core.

SCOPE OF THE INVENTION

The above description presents the best mode contemplated of carrying out the present invention as depicted by the embodiment disclosed. The features illustrated by this embodiment provide the advantages of this invention. This invention is, however, susceptible to modifications and alternate constructions from the embodiment shown in the drawing and description above. Consequently, it is not the intention to limit it to the particular embodiment disclosed. On the contrary, the intention is to cover all modifications and alternates falling within the scope of the invention as generally expressed by the following claims.