Nuclear reactor vessel support system
A nuclear reactor support system that, in one embodiment, includes a reactor vessel, a reactor core disposed within the reactor vessel, an upper portion of the reactor vessel located above a ground plane and a lower portion of the reactor vessel located below the ground plane. The support system further includes a first flange fixedly attached to the upper portion of the reactor vessel and contacting the ground plane, the first flange supporting the reactor vessel, a second flange fixedly attached to the upper portion of the reactor vessel above the ground plane, the second flange spaced vertically apart from the first flange, and a plurality of welded lugs extending vertically between the first and second flanges. The first flange supports the entire weight of the reactor vessel in a cantilevered manner.
1. A nuclear reactor support system comprising:
an elongated reactor vessel having a weight and an internal cavity configured for containing a primary coolant, the reactor vessel extending along a substantially vertical axis;
a reactor core disposed within the internal cavity;
an upper portion of the reactor vessel located above a ground plane and a lower portion of the reactor vessel located below the ground plane;
the upper portion of the reactor vessel comprising a primary coolant outlet port fluidly coupled to the cavity;
a first flange fixedly attached to the upper portion of the reactor vessel and contacting the ground plane, the first flange supporting the reactor vessel; a second flange fixedly attached to the upper portion of the reactor vessel above the ground plane, the second flange spaced vertically apart from the first flange; and
a plurality of welded lugs extending vertically between the first and second flanges.
2. The system according to claim 1 , wherein the first flange supports the entire weight of the reactor vessel in a cantilevered manner.
3. The system according to claim 2 , wherein the lower portion of the reactor vessel is disposed in a reactor well below the ground plane.
4. The system according to claim 3 , wherein a bottom of the reactor vessel is spaced vertically above a floor of the reactor well.
5. The system according to claim 4 , wherein the lower portion represents a majority of a length of the reactor vessel.
6. The system according to claim 1 , wherein the upper portion of the reactor vessel further comprises a primary coolant inlet port located above the ground plane and fluidly coupled to the cavity.
7. The system according to claim 6 , wherein the primary coolant inlet and outlet ports are fluidly coupled to a steam generator.
8. The system according to claim 1 , wherein the ground plane is defined by a top surface of a concrete slab.
9. The system according to claim 8 , wherein the concrete slab forms a portion of a reactor well which accepts the lower portion of the reactor vessel, the reactor well further comprising a plurality of sidewalls and a floor.
10. The system according to claim 9 , wherein a bottom end of the reactor vessel is spaced apart from the floor of the reactor well such that the first flange supports the reactor vessel in a cantilevered manner.
11. The system according to claim 2 , further comprising a domed head detachably coupled to the upper portion above the first flange.
12. The system according to claim 11 , wherein the upper portion of the reactor vessel is terminated with a first bolting flange coupled to a mating second bolting of the domed head via a plurality of bolts.