Reactor pressure vessel
View Patent ↗A reactor pressure vessel supports the flanges of a core barrel assembly and an upper support plate. These flanges have aligned holes for diverting inlet coolant water to the vessel head for cooling the head. The aligned holes have different cross-sectional areas for controlling unexpected backflow of coolant water from the vessel head around the periphery of the upper support plate.
1. A reactor pressure vessel (RPV) for containing nuclear fuel assemblies in coolant water, comprising:
a vessel body having an internal support ledge;
a removable top head having a flange and an inner surface defining a head cavity;
a core barrel assembly having a flange supported on the internal support ledge for supporting the fuel assemblies, the core barrel assembly flange having holes extending between a lower flange surface and an upper flange surface, each hole disposed inwardly of the internal support ledge, each hole having a cross-sectional area; and
an upper support plate having a flange with a lower flange surface and an upper flange surface and a periphery extending between the lower flange surface and the upper flange surface, the lower surface of the upper support plate flange disposed above and spaced from the upper surface of the core barrel assembly flange, the lower surface of the upper support plate flange and the upper surface of the core barrel assembly flange defining an inter-flange cavity, the periphery of the upper support plate flange and the vessel body defining a coolant water leak way in flow communication with the inter-flange cavity, the upper support plate flange having holes extending between its lower surface and its upper surface and aligned with the holes in the core barrel assembly, the holes in the upper support plate flange disposed in coolant flow communication with the holes in the core barrel assembly flange and with the inter-flange cavity and the coolant water leak way, the holes in the upper support plate flange disposed inwardly of the removable top head flange and opening to the head cavity for discharging coolant water along the inner surface of the removable top head, each upper support plate flange hole having a cross-sectional area;
wherein the cross-sectional area of the core barrel assembly flange hole is smaller than the cross-sectional area of the aligned upper support plate flange hole for controlling leakage of coolant water in the head cavity around the periphery of the upper support plate flange and into the inter-flange cavity and induction of the leaked coolant water by the coolant water flowing into the holes in the upper support plate flange.
2. The reactor pressure vessel of claim 1 , wherein the cross-sectional area of each hole in the core barrel assembly flange varies such that the cross-sectional area of the hole at the lower surface of the core barrel assembly flange is smaller than the cross-sectional area of the hole at the upper surface of the core barrel assembly flange.
3. The RPV of claim 1 , wherein the cross-sectional area of each hole in the upper support plate flange varies such that the cross-sectional area of the hole at the lower surface of the upper support plate flange is smaller than the cross-sectional area of the hole at the upper surface of the upper support plate flange.
4. The RPV of claim 1 , wherein the holes in the core barrel assembly flange are circular.
5. The RPV of claim 4 , wherein the holes in the core barrel assembly flange have a diameter of about 2¼ inches.
6. The RPV of claim 5 , wherein the holes in the upper support plate flange are circular.
7. The RPV of claim 6 , wherein the holes in the upper support plate flange have a diameter of about 3¼ inches.
8. The RPV of claim 1 , wherein the holes in the core barrel assembly flange are oblong slots.
9. The RPV of claim 1 , wherein the holes in the upper support plate assembly flange are oblong slots.
10. The RPV of claim 1 , wherein the ratio of the cross-sectional area of the core barrel assembly flange hole to the cross-sectional area of the aligned upper support plate flange hole is about 0.69.
11. A reactor pressure vessel (RPV) for containing nuclear fuel assemblies in coolant water, comprising:
a vessel body having an internal support ledge;
a removable top head having a flange and an inner surface defining a head cavity;
a core barrel assembly having a flange supported on the internal support ledge for supporting the fuel assemblies;
an upper support plate having a flange with a lower flange surface and an upper flange surface and a periphery extending between the lower flange surface and the upper flange surface, the lower surface of the upper support plate flange disposed above and spaced from the upper surface of the core barrel assembly flange, the lower surface of the upper support plate flange and the upper surface of the core barrel assembly flange defining an inter-flange cavity; and
means for diverting coolant water flow into the head cavity from the inter-flange cavity while controlling coolant water leakage from the head cavity into the inter-flange cavity.
12. The reactor pressure vessel of claim 11 , wherein the means diverts the coolant water flow while reducing entrainment of leaked coolant water in the inter-flange cavity by the flowing coolant water.
13. In a reactor pressure vessel (RPV) for containing nuclear fuel assemblies in coolant water, comprising:
a vessel body having an internal support ledge;
a removable top head having a flange and an inner surface defining a head cavity;
a core barrel assembly having a flange supported on the internal support ledge for supporting the fuel assemblies, the core barrel assembly flange having an upper surface; and
an upper support plate having a flange with a lower flange surface and an upper flange surface and a periphery extending between the lower flange surface and the upper flange surface, the lower surface of the upper support plate flange disposed above and spaced from the upper surface of the core barrel assembly flange, the lower surface of the upper support plate flange and the upper surface of the core barrel assembly flange defining an inter-flange cavity;
a method of diverting a flow of coolant water into the top head, comprising the step of:
controlling the flow of coolant water into the head cavity from the inter-flange cavity while controlling leakage of coolant water from the head cavity around the periphery of the upper support plate flange into the inter-flange cavity.
14. The method of claim 13 , wherein the step of diverting the flow of coolant water comprises: controlling entrainment of coolant water leaking around the periphery of the upper support plate flange by the flowing coolant water.