Systems and methods for enhancing isolation of high-temperature reactor containments

Patent metadata

Field	Value
Publication number	US-11189384-B2
Application number	US-201715684062-A
Country	US
Kind code	B2
Filing date	Aug 23, 2017
Priority date	Nov 4, 2013
Publication date	Nov 30, 2021
Grant date	Nov 30, 2021

Abstract

A high-temperature containment-isolation system for transferring heat from a nuclear reactor containment to a high-pressure heat exchanger is presented. The system uses a high-temperature, low-volatility liquid coolant such as a molten salt or a liquid metal, where the coolant flow path provides liquid free surfaces a short distance from the containment penetrations for the reactor hot-leg and the cold-leg, where these liquid free surfaces have a cover gas maintained at a nearly constant pressure and thus prevent high-pressures from being transmitted into the reactor containment, and where the reactor vessel is suspended within a reactor cavity with a plurality of refractory insulator blocks disposed between an actively cooled inner cavity liner and the reactor vessel.

First claim

What is claimed is:

1. A high-temperature containment-isolation system for an HTR, comprising:
a reactor vessel disposed inside a reactor cavity having an outer containment wall;
a hot-well vessel with a hot-leg pipe coupled to the reactor vessel at a hot-leg penetration of the outer containment wall, said hot-well vessel having an interior surface;
wherein the hot-leg pipe provides a coolant liquid flow path from the hot-leg penetration through the hot-well vessel;
wherein a section of the interior surface of the hot-well vessel is a liquid-free surface; and
wherein the liquid-free surface has a cover gas maintained at a constant pressure and thus prevents coolant overpressures from being transmitted into the reactor vessel.

2. A system as recited in claim 1 , further comprising:
an isolation valve within the hot-well vessel controlling the hot-leg coolant flow path into the hot-well vessel;
wherein hot coolant exiting the reactor vessel flows through the isolation valve into the hot-well vessel.

3. A system as recited in claim 1 , wherein the hot-well vessel further comprises a submerged centrifugal pump that circulates the hot coolant through a crossover-leg.

4. A system as recited in claim 3 , wherein the hot-well vessel has sufficient volume to accommodate level changes due to thermal expansion of the coolant and level changes within the system due to flow caused by operation of the pump.

5. A system as recited in claim 2 , wherein the isolation valve comprises a gate valve to seal and isolate the hot-leg pipe and reactor vessel from the hot-well vessel.

Assignees

• Univ California

Inventors

• Peterson Per F

Classifications

• G21C11/08 Primary

  Thermal shields; Thermal linings, i.e. for dissipating heat from gamma radiation which would otherwise heat an outer biological shield {; Thermal insulation} · CPC title

• G21C15/12

  from pressure vessel; from containment vessel · CPC title

• Y02E30/30

  Nuclear fission reactors · CPC title

• G21C13/10

  Means for preventing contamination in the event of leakage, {e.g. double wall} · CPC title

• G21C13/02

  Details · CPC title