Patent Number: 
Section: claims

1. An apparatus comprising:a nuclear reactor including a nuclear reactor core comprising fissile material disposed in a pressure vessel and immersed in primary coolant water at an operating pressure higher than atmospheric pressure;at least one reactor coolant pump including a motor and an impeller, the impeller being disposed within the pressure vessel;a containment structure containing the nuclear reactor;a reactor coolant inventory and purification system connected with the pressure vessel by make-up and letdown lines, the reactor coolant inventory and purification system rated to operate at the operating pressure and including a high pressure heat exchanger disposed inside the containment structure and connected to the pressure vessel by the make-up and letdown lines and configured to operate responsive to a safety event at the operating pressure to remove heat from the primary coolant water in the pressure vessel;a make-up water tank containing a supply of purified water as make-up primary coolant;a first pump disposed inside the containment structure, the first pump having an inlet connected to the letdown line, and an outlet connected to the high pressure heat exchanger and being configured to flow primary coolant water through the high pressure heat exchanger; anda second pump disposed outside the containment structure, the second pump having an inlet connected to the make-up water tank, an outlet connected to the make-up line and being configured to inject purified make-up water into the pressure vessel via the make-up line at the operating pressure during normal power operations. 2. The apparatus of claim 1, wherein the high pressure heat exchanger of the reactor coolant inventory and purification system is configured to expel the removed heat to a component cooling water system supporting the nuclear reactor. 3. The apparatus of claim 1, wherein the high pressure heat exchanger of the reactor coolant inventory and purification system is configured to operate responsive to the operating pressure exceeding a first pressure threshold. 4. The apparatus of claim 3, further comprising:an emergency core cooling system configured to operate to depressurize the nuclear reactor responsive to the operating pressure exceeding a second pressure threshold higher than the first pressure threshold. 5. The apparatus of claim 1, further comprising:a steam generator disposed inside the containment structure and integral with or connected with the nuclear reactor, the steam generator heating secondary coolant water using primary coolant water disposed in or supplied by the nuclear reactor;an auxiliary condenser disposed outside the containment structure, the auxiliary condenser being connected to the steam generator by piping; anda valve disposed on the piping connecting the auxiliary condenser to the steam generator, the valve being configured to open independently of the isolation valve of the main steam line to allow secondary coolant water from the steam generator to flow through the auxiliary condenser so as to expel heat from the primary coolant water outside containment. 6. The apparatus of claim 5, wherein the auxiliary condenser is an air cooled condenser. 7. The apparatus of claim 6, wherein the auxiliary condenser includes battery driven fans providing air cooling. 8. The apparatus of claim 5, further comprising:an ultimate heat sink (UHS), the auxiliary condenser not expelling heat from the primary coolant water into the UHS. 9. The apparatus of claim 5, further comprising:an ultimate heat sink comprising a pool of water disposed on top of and in thermal contact with the containment structure. 10. An apparatus comprising:a nuclear reactor including a nuclear reactor core comprising fissile material disposed in a pressure vessel and immersed in primary coolant water at an operating pressure higher than atmospheric pressure;at least one reactor coolant pump including a motor and an impeller, the impeller being disposed within the pressure vessel;a containment structure containing the nuclear reactor; anda reactor coolant inventory and purification system connected with the pressure vessel by make-up and letdown lines, the reactor coolant inventory and purification system rated to operate at the operating pressure and including a high pressure heat exchanger disposed inside the containment structure and connected to the pressure vessel by the make-up and letdown lines and configured to remove heat from the primary coolant water, a make-up water tank containing a supply of purified water as make-up primary coolant, a first pump disposed inside the containment structure, the first pump having an inlet connected to the letdown line, and outlet connected to the high pressure heat exchanger and being configured to flow primary coolant water through the high pressure heat exchanger, and a second pump disposed outside the containment structure, the second pump having an inlet connected to the make-up water tank, an outlet connected to the make-line and being configured to inject purified make-up water into the pressure vessel via the make-up line at the operating pressure during normal power operations. 11. The apparatus of claim 10, wherein the reactor coolant inventory and purification system is configured to operate the second pump responsive to the primary coolant water level in the pressure vessel decreasing below a first water level threshold. 12. The apparatus of claim 11, further comprising:an emergency core cooling system configured to operate to depressurize the nuclear reactor responsive to the primary coolant water level in the pressure vessel decreasing below a second water level threshold lower than the first water level threshold. 13. The apparatus of claim 10 wherein the reactor coolant inventory and purification system further includes:a tank containing borated water, the second pump of the reactor coolant inventory and purification system configured to inject borated make-up water from the tank into the pressure vessel via the make-up line at the operating pressure.