Passive power production during a nuclear station blackout

Patent metadata

Field	Value
Publication number	US-9536629-B2
Application number	US-201313764804-A
Country	US
Kind code	B2
Filing date	Feb 12, 2013
Priority date	Jul 24, 2012
Publication date	Jan 3, 2017
Grant date	Jan 3, 2017

Abstract

Apparatus for passively generating electric power during a nuclear power station blackout by utilizing the temperature difference between the hot inlet of a residual heat removal circuit and the surrounding containment environment. A heat engine, such as a thermoelectric generator, a Stirling Cycle Engine or Rankine Cycle Engine, is coupled in heat exchange relationship with an uninsulated portion of the inlet to a passive residual heat removal heat exchanger and/or passive residual heat removal heat exchanger channel head to generate the power required to operate essential equipment needed to maintain the nuclear power station in a safe condition during a loss of normal onsite and offsite power.

First claim

What is claimed is:

1. A nuclear power plant having a reactor with a coolant circulating within a fissile nuclear core to carry heat generated within the core to a utilization circuit for creating useful work, including;
a coolant residual heat removal circuit for dissipating residual heat generated in the core after the reactor has been shut down in the unlikely event an abnormal operating condition is encountered, the coolant residual heat removal circuit including:
a residual heat removal conduit for conveying a volume of a coolant from the reactor core through the residual heat removal circuit, wherein the residual heat removal conduit includes an uninsulated section;
a plurality of heat engines respectively having a first component part in heat exchange relationship with the uninsulated section and a second component part spaced from the uninsulated section and in heat exchange relationship with the environment surrounding the uninsulated section and responsive to a temperature difference between the residual heat removal conduit and the environment surrounding the uninsulated section to generate either electrical or mechanical power as an auxiliary power source to assist management of the abnormal operating condition; and
a heat conductive clamp having a plurality of recesses in an outer surface of the clamp with at least some of the recesses respectively fastening at least a portion of the first component part of a corresponding one of the plurality of heat engines in substantially close proximity to an outer surface of the uninsulated section.

2. The nuclear power plant of claim 1 wherein the heat engine is a thermoelectric generator.

3. The nuclear power plant of claim 1 wherein the heat engine is either a Rankine cycle engine or a Stirling cycle engine.

4. The nuclear power plant of claim 1 wherein the residual heat removal circuit includes a Passive Residual Heat Removal heat exchanger having a channel head and the uninsulated section is on a piping section leading to the channel head and/or on the channel head.

5. The nuclear power plant of claim 1 including a heat removal and a monitoring system for managing a shutdown of the nuclear plant in the unlikely event of the abnormal operating condition wherein one or more of the heat removal and the monitoring systems is at least in part operated by an onsite, independent, passively activated power source wherein the auxiliary power source is connected to and extends the operating life of the onsite, independent, passively activated power source.

6. The nuclear power plant of claim 1 wherein the auxiliary power source is only active when coolant flow has been initiated through the residual heat removal circuit.

Assignees

• Westinghouse Electric Co Llc

Inventors

• Dederer Jeffrey T
• Perego Catherine M

Classifications

• G21C15/26

  by convection, e.g. using chimneys, using divergent channels · CPC title

• G21C15/18 Primary

  Emergency cooling arrangements; Removing shut-down heat · CPC title

• G21D3/06

  responsive to faults within the plant (in the reactor G21C9/00) · CPC title

• Y02E30/40

  Cross-Sectional Technologies · mapped topic

• Y02E30/30

  Nuclear fission reactors · CPC title