Integrated emergency core cooling system condenser for pressurized water reactor
View Patent ↗A pressurized water nuclear reactor (PWR) includes a pressure vessel having a lower portion containing a nuclear reactor core comprising a fissile material and an upper portion defining an internal pressurizer volume. A condenser is secured to, and optionally supported by, the upper portion of the pressure vessel. A condenser inlet is in fluid communication with the internal pressurizer volume. A heat sink is in fluid communication with the condenser such that the condenser operates as a passive heat exchanger to condense steam from the internal pressurizer volume into condensate while rejecting heat to the heat sink. A condenser outlet connects with the pressure vessel to return condensate to the pressure vessel. A single metal forging having a first end welded to the pressure vessel and a second end welded to the condenser inlet may provide the fluid communication between the condenser inlet and the internal pressurizer volume.
1. An apparatus comprising:
a pressurized water reactor (PWR) disposed within a containment structure, the PWR including a pressure vessel having a lower portion containing a nuclear reactor core comprising a fissile material and an upper portion defining an internal pressurizer volume;
a baffle plate disposed in the pressure vessel between the lower portion and the upper portion so that the baffle plate separates the internal pressurizer volume from the lower portion;
at least one steam pressure control device provided in the internal pressurizer volume;
a condenser including a condenser inlet and a condenser outlet, the condenser being supported only by the upper portion of the pressure vessel; and
a steam line connecting the internal pressurizer volume with the condenser inlet of the condenser,
wherein the condenser outlet is in fluid communication with a sealed volume contained by the pressure vessel at a point below the steam line, and
wherein the condenser is a passive heat exchanger that condenses steam flowing into the condenser from the internal pressurizer volume while rejecting heat to a heat sink comprising a body of water that is disposed external to the containment structure, the condensed steam flowing into the sealed volume contained by the pressure vessel via the condenser outlet.
2. The apparatus of claim 1 , wherein the condenser is supported by the upper portion of the pressure vessel via the steam line connecting the internal pressurizer volume with the condenser inlet of the condenser.
3. The apparatus of claim 1 , further comprising:
a steam generator disposed inside the pressure vessel;
wherein the condenser outlet is in fluid communication with the sealed volume contained by the pressure vessel at an upper plenum between the internal pressurizer volume and the steam generator.
4. The apparatus of claim 1 , wherein the steam line comprises a single metal forging having a first end welded to the pressure vessel and a second end welded to the condenser.
5. The apparatus of claim 1 , wherein a pressure drop across the steam line is less than one-third of a pressure drop across orifices of the steam line.
6. An apparatus comprising:
a pressurized water reactor (PWR) disposed within a containment structure, the PWR including a pressure vessel having a lower portion containing a nuclear reactor core comprising a fissile material and an upper portion defining an internal pressurizer volume;
a baffle plate disposed in the pressure vessel between the lower portion and the upper portion so that the baffle plate separates the internal pressurizer volume from the lower portion;
at least one steam pressure control device provided in the internal pressurizer volume;
a condenser secured to the upper portion of the pressure vessel and having a condenser inlet in fluid communication with the internal pressurizer volume;
a heat sink in fluid communication with the condenser, the condenser operating as a passive heat exchanger to condense steam from the internal pressurizer volume into condensate while rejecting heat to the heat sink, the heat sink being located external to the containment structure; and
a condenser outlet connected with the pressure vessel to flow the condensate back into the pressure vessel.
7. The apparatus of claim 6 , wherein the condenser is supported at an elevated position respective to the nuclear reactor core by the pressure vessel.
8. The apparatus of claim 6 , further comprising:
a single metal forging providing fluid communication between the condenser inlet and the internal pressurizer volume, the single metal forging having a first end welded to the pressure vessel and a second end welded to the condenser inlet.
9. The apparatus of claim 8 , wherein the single metal forging is a single steel or steel alloy forging.
10. The apparatus of claim 6 , further comprising:
a steam generator disposed inside the pressure vessel;
wherein the condenser outlet connects with the pressure vessel above an upper end of the steam generator.
11. The apparatus of claim 6 , further comprising: said heat sink comprising a body of water in fluid communication with the condenser.
12. The apparatus of claim 6 , wherein:
the condenser comprises a tube bundle with a surrounding shell;
the heat sink is in fluid communication with one of the tube-side and the shell-side of the tube bundle; and
the condenser inlet is in fluid communication with the other of the tube-side and the shell-side of the tube bundle.