Method and system for the thermoelectric conversion of nuclear reactor generated heat

• US 20100260307A1
• Filed: 07/31/2009
• Published: 10/14/2010
• Est. Priority Date: 04/13/2009
• Status: Abandoned Application

• Current Assignee: TerraPower LLC
• Original Assignee: Searete LLC (Intellectual Ventures LLC)
• Inventors: Weaver, Thomas, Ishikawa, Muriel Y., Myhrvold, Nathan P., Wood, Lowell L. JR., Hyde, Roderick A., Walter, Joshua C., Wood, Victoria Y.H.
• Application Number:
  US12/462,332
• Publication Number:
  US 20100260307A1
• Time in Patent Office: Days
• US Class Current: 376/299
• CPC Class Codes: G21C 1/026 Reactors not needing refueling, i.e. reactors of the type breed-and-burn, e.g. travelling or deflagration wave reactors or seed-blanket reactors
• CPC Class Codes: G21D 3/00 Control of nuclear power plant control of nuclear reaction in general G21C7/00
• CPC Class Codes: G21D 3/04 Safety arrangements emergency protection of reactor G21C9/00
• CPC Class Codes: G21D 3/08 Regulation of any parameters in the plant
• CPC Class Codes: G21D 7/04 using thermoelectric elements or thermoionic convertersstructural combination of fuel element with thermoelectric element or with thermoionic converters G21C3/40 , G21H1/10; thermoelectric elements per se H10N10/00, H10N15/00
• CPC Class Codes: Y02E 30/00 Energy generation of nuclear origin
• CPC Class Codes: Y02E 30/30 Nuclear fission reactors

Abstract

A method and system for the thermoelectric conversion of nuclear reactor generated heat including upon a nuclear reactor system shutdown event, thermoelectrically converting nuclear reactor generated heat to electrical energy and supplying the electrical energy to a mechanical pump of the nuclear reactor system.

Claims

1-129. -129. (canceled)

130. A system, comprising:

at least one thermoelectric device for converting nuclear reactor generated heat to electrical energy upon a nuclear reactor system shutdown event; and

at least one electrical output of the at least one thermoelectric device electrically coupled to at least one mechanical pump of the nuclear reactor system for supplying the electrical energy to the at least one mechanical pump of the nuclear reactor system.

131. The system of claim 130, wherein the at least one thermoelectric device for converting nuclear reactor generated heat to electrical energy upon a nuclear reactor system shutdown event comprises:

at least one thermoelectric device for converting nuclear reactor generated heat to electrical energy during initiation of a nuclear reactor shutdown.

132. The system of claim 130, wherein the at least one thermoelectric device for converting nuclear reactor generated heat to electrical energy upon a nuclear reactor system shutdown event comprises:

at least one thermoelectric device for converting nuclear reactor generated heat to electrical energy preceding initiation of a nuclear reactor shutdown.

133. The system of claim 130, wherein the at least one thermoelectric device for converting nuclear reactor generated heat to electrical energy upon a nuclear reactor system shutdown event comprises:

at least one thermoelectric device for converting nuclear reactor generated heat to electrical energy following initiation of a nuclear reactor shutdown.

134. The system of claim 130, wherein the at least one mechanical pump of the nuclear reactor system comprises:

at least one mechanical pump of the nuclear reactor system coupled to at least one coolant system of the nuclear reactor system.

135. The system of claim 134, wherein the at least one mechanical pump of the nuclear reactor system coupled to at least one coolant system of the nuclear reactor system comprises:

at least one mechanical pump of the nuclear reactor system coupled to at least one coolant system of the nuclear reactor system, the at least one mechanical pump in series with at least one additional mechanical pump.

136. The system of claim 134, wherein the at least one mechanical pump of the nuclear reactor system coupled to at least one coolant system of the nuclear reactor system comprises:

at least one mechanical pump of the nuclear reactor system coupled to at least one coolant system of the nuclear reactor system, the at least one mechanical pump in parallel with at least one additional mechanical pump.

137. The system of claim 134, wherein the at least one mechanical pump of the nuclear reactor system coupled to at least one coolant system of the nuclear reactor system comprises:

at least one mechanical pump of the nuclear reactor system coupled to at least one coolant system of the nuclear reactor system, the at least one mechanical pump supplying supplemental pumping power to the at least one coolant system.

138. The system of claim 137, wherein the at least one mechanical pump of the nuclear reactor system coupled to at least one coolant system of the nuclear reactor system, the at least one mechanical pump supplying supplemental pumping power to the at least one coolant system comprises:

at least one mechanical pump of the nuclear reactor system coupled to at least one coolant system of the nuclear reactor system, the at least one mechanical pump supplying supplemental pumping power to the at least one coolant system, the supplemental pumping power enhancing a pumping mass flow rate.

139. The system of claim 134, wherein the at least one mechanical pump of the nuclear reactor system coupled to at least one coolant system of the nuclear reactor system comprises:

at least one mechanical pump of the nuclear reactor system coupled to at least one coolant system of the nuclear reactor system, the at least one mechanical pump supplying auxiliary pumping power to the at least one coolant system.

140. The system of claim 139, wherein the at least one mechanical pump of the nuclear reactor system coupled to at least one coolant system of the nuclear reactor system, the at least one mechanical pump supplying auxiliary pumping power to the at least one coolant system comprises:

at least one mechanical pump of the nuclear reactor system coupled to at least one coolant system of the nuclear reactor system, the at least one mechanical pump supplying auxiliary pumping power to the at least one coolant system, the auxiliary pumping power establishing a coolant mass flow rate.

141. The system of claim 140, wherein the at least one mechanical pump of the nuclear reactor system coupled to at least one coolant system of the nuclear reactor system, the at least one mechanical pump supplying auxiliary pumping power to the at least one coolant system, the auxiliary pumping power establishing a coolant mass flow rate comprises:

at least one mechanical pump of the nuclear reactor system coupled to at least one coolant system of the nuclear reactor system, the at least one mechanical pump supplying auxiliary pumping power to the at least one coolant system, the auxiliary pumping power establishing a coolant mass flow rate, the coolant mass flow rate maintaining circulation in at least one reactor coolant pool, at least one reactor coolant pressure vessel, at least one reactor heat exchange loop, or at least one ambient coolant.

142. The system of claim 130, wherein the at least one mechanical pump of the nuclear reactor system comprises:

at least one mechanical pump of the nuclear reactor system circulating coolant through a portion of at least one nuclear reactor core or a portion of at least one heat exchanger.

143. The system of claim 130, wherein the at least one mechanical pump of the nuclear reactor system comprises:

at least one mechanical pump of the nuclear reactor system circulating at least one liquid coolant.

144. The system of claim 143, wherein the at least one mechanical pump of the nuclear reactor system circulating at least one liquid coolant comprises:

at least one mechanical pump of the nuclear reactor system circulating at least one liquid metal coolant.

145. The system of claim 143, wherein the at least one mechanical pump of the nuclear reactor system circulating at least one liquid coolant comprises:

at least one mechanical pump of the nuclear reactor system circulating at least one liquid salt coolant.

146. The system of claim 143, wherein the at least one mechanical pump of the nuclear reactor system circulating at least one liquid coolant comprises:

at least one mechanical pump of the nuclear reactor system circulating at least one liquid water coolant.

147. The system of claim 143, wherein the at least one mechanical pump of the nuclear reactor system circulating at least one liquid coolant comprises:

at least one mechanical pump of a pool type nuclear reactor system circulating at least one liquid coolant.

148. The system of claim 130, at least one mechanical pump of the nuclear reactor system comprises:

at least one mechanical pump of the nuclear reactor system circulating at least one pressurized gas coolant.

149. The system of claim 130, wherein the at least one mechanical pump of the nuclear reactor system comprises:

at least one mechanical pump of the nuclear reactor system circulating at least one mixed phase coolant.

150. The system of claim 130, wherein the nuclear reactor of the nuclear reactor system comprises:

a thermal spectrum nuclear reactor, a fast spectrum nuclear reactor, a multi-spectrum nuclear reactor, a breeder nuclear reactor, or a traveling wave nuclear reactor.

151. The system of claim 130, wherein the at least one thermoelectric device for converting nuclear reactor generated heat to electrical energy upon a nuclear reactor system shutdown event comprises:

at least one thermoelectric device for converting nuclear reactor generated decay heat to electrical energy upon a nuclear reactor system shutdown event.

152. The system of claim 130, wherein the at least one thermoelectric device for converting nuclear reactor generated heat to electrical energy upon a nuclear reactor system shutdown event comprises:

at least one thermoelectric device for converting nuclear reactor generated residual heat to electrical energy upon a nuclear reactor system shutdown event.

153. The system of claim 130, wherein the nuclear reactor system shutdown event is established by at least one reactor control system.

154. The system of claim 153, wherein the at least one reactor control system comprises:

at least one reactor control system responsive to at least one signal from at least one safety system.

155. The system of claim 154, wherein the at least one reactor control system responsive to at least one signal from at least one safety system comprises:

at least one reactor control system responsive to at least one signal from at least one safety system, the at least one safety system of the nuclear reactor system responsive to at least one sensed condition of the nuclear reactor system.

156. The system of claim 155, wherein the at least one reactor control system responsive to at least one signal from at least one safety system, the at least one safety system of the nuclear reactor system responsive to at least one sensed condition of the nuclear reactor system comprises:

at least one reactor control system responsive to at least one signal from at least one safety system, the at least one safety system of the nuclear reactor system responsive to at least one sensed external condition of the nuclear reactor system.

157. The system of claim 155, wherein the at least one reactor control system responsive to at least one signal from at least one safety system, the at least one safety system of the nuclear reactor system responsive to at least one sensed condition of the nuclear reactor system comprises:

at least one reactor control system responsive to at least one signal from at least one safety system, the at least one safety system of the nuclear reactor system responsive to at least one sensed internal condition of the nuclear reactor system.

158. The system of claim 130, wherein the nuclear reactor system shutdown event is established by at least one signal from an operator.

159. The system of claim 130, wherein the at least one thermoelectric device for converting nuclear reactor generated heat to electrical energy upon a nuclear reactor system shutdown event comprises:

at least one thermoelectric junction for converting nuclear reactor generated heat to electrical energy upon a nuclear reactor system shutdown event.

160. The system of claim 159, wherein the at least one thermoelectric junction for converting nuclear reactor generated heat to electrical energy upon a nuclear reactor system shutdown event comprises:

at least one semiconductor-semiconductor junction for converting nuclear reactor generated heat to electrical energy upon a nuclear reactor system shutdown event.

161. The system of claim 160, wherein the at least one semiconductor-semiconductor junction for converting nuclear reactor generated heat to electrical energy upon a nuclear reactor system shutdown event comprises:

at least one p-type/n-type junction for converting nuclear reactor generated heat to electrical energy upon a nuclear reactor system shutdown event.

162. The system of claim 159, wherein the at least one thermoelectric junction for converting nuclear reactor generated heat to electrical energy upon a nuclear reactor system shutdown event comprises:

at least one metal-metal junction for converting nuclear reactor generated heat to electrical energy upon a nuclear reactor system shutdown event.

163. The system of claim 130, wherein the at least one thermoelectric device for converting nuclear reactor generated heat to electrical energy upon a nuclear reactor system shutdown event comprises:

at least one nanofabricated thermoelectric device for converting nuclear reactor generated heat to electrical energy upon a nuclear reactor system shutdown event.

164. The system of claim 130, wherein the at least one thermoelectric device for converting nuclear reactor generated heat to electrical energy upon a nuclear reactor system shutdown event comprises:

at least one thermoelectric device optimized for a specified range of operating characteristics for converting nuclear reactor generated heat to electrical energy upon a nuclear reactor system shutdown event.

165. The system of claim 130, wherein the at least one thermoelectric device for converting nuclear reactor generated heat to electrical energy upon a nuclear reactor system shutdown event comprises:

at least one thermoelectric device optimized for a first range of operating characteristics and at least one additional thermoelectric device optimized for a second range of operating characteristics, the second range of operating characteristics different from the first range of operating characteristics, for converting nuclear reactor generated heat to electrical energy upon a nuclear reactor system shutdown event.

166. The system of claim 130, wherein the at least one thermoelectric device for converting nuclear reactor generated heat to electrical energy upon a nuclear reactor system shutdown event comprises:

at least one thermoelectric device, the thermoelectric device having at least a first portion in thermal communication with a first portion of the nuclear reactor system and at least a second portion in thermal communication with a second portion of the nuclear reactor system, for converting nuclear reactor generated heat to electrical energy upon a nuclear reactor system shutdown event.

167. The system of claim 166, wherein the at least one thermoelectric device, the thermoelectric device having at least a first portion in thermal communication with a first portion of the nuclear reactor system and at least a second portion in thermal communication with a second portion of the nuclear reactor system, for converting nuclear reactor generated heat to electrical energy upon a nuclear reactor system shutdown event. comprises:

at least one thermoelectric device, the thermoelectric device having at least a first portion in thermal communication with at least one heat source of the nuclear reactor system, for converting nuclear reactor generated heat to electrical energy upon a nuclear reactor system shutdown event.

168. The system of claim 167, wherein the at least one thermoelectric device, the thermoelectric device having at least a first portion in thermal communication with at least one heat source of the nuclear reactor system, for converting nuclear reactor generated heat to electrical energy upon a nuclear reactor system shutdown event comprises:

at least one thermoelectric device, the thermoelectric device having at least a first portion in thermal communication with at least a portion of a nuclear reactor core, at least a portion of at least one pressure vessel, at least a portion of at least one containment vessel, at least a portion of at least one coolant loop, at least a portion of at least one coolant pipe, at least a portion of at least one heat exchanger, or at least a portion of a coolant of the nuclear reactor system, for converting nuclear reactor generated heat to electrical energy upon a nuclear reactor system shutdown event.

169. The system of claim 166, wherein the at least one thermoelectric device, the thermoelectric device having at least a first portion in thermal communication with a first portion of the nuclear reactor system and at least a second portion in thermal communication with a second portion of the nuclear reactor system, for converting nuclear reactor generated heat to electrical energy upon a nuclear reactor system shutdown event comprises:

at least one thermoelectric device, the thermoelectric device having at least a second portion in thermal communication with a second portion of the nuclear reactor system, the second portion of the nuclear reactor system at a lower temperature than the first portion of the nuclear reactor system, for converting nuclear reactor generated heat to electrical energy upon a nuclear reactor system shutdown event.

170. The system of claim 169, wherein the at least one thermoelectric device, the thermoelectric device having at least a second portion in thermal communication with a second portion of the nuclear reactor system, the second portion of the nuclear reactor system at a lower temperature than the first portion of the nuclear reactor system, for converting nuclear reactor generated heat to electrical energy upon a nuclear reactor system shutdown event comprises:

at least one thermoelectric device, the thermoelectric device having at least a second portion in thermal communication with at least a portion of at least one coolant loop, at least a portion of at least one coolant pipe, at least a portion of at least one heat exchanger, at least a portion of a coolant of the nuclear reactor system, or at least a portion of at least one environmental reservoir, for converting nuclear reactor generated heat to electrical energy upon a nuclear reactor system shutdown event.

171. The system of claim 130, wherein the at least one thermoelectric device for converting nuclear reactor generated heat to electrical energy upon a nuclear reactor system shutdown event comprises:

at least two series coupled thermoelectric devices for converting nuclear reactor generated heat to electrical energy upon a nuclear reactor system shutdown event.

172. The system of claim 130, wherein the at least one thermoelectric device for converting nuclear reactor generated heat to electrical energy upon a nuclear reactor system shutdown event comprises:

at least two parallel coupled thermoelectric devices for converting nuclear reactor generated heat to electrical energy upon a nuclear reactor system shutdown event.

173. The system of claim 130, wherein the at least one thermoelectric device for converting nuclear reactor generated heat to electrical energy upon a nuclear reactor system shutdown event comprises:

at least one thermoelectric module for converting nuclear reactor generated heat to electrical energy upon a nuclear reactor system shutdown event.

174. The system of claim 130, wherein the at least one thermoelectric device for converting nuclear reactor generated heat to electrical energy upon a nuclear reactor system shutdown event comprises:

at least one thermoelectric device sized to meet at least one selected operational requirement of the nuclear reactor system for converting nuclear reactor generated heat to electrical energy upon a nuclear reactor system shutdown event.

175. The system of claim 174, wherein the at least one thermoelectric device sized to meet at least one selected operational requirement of the nuclear reactor system for converting nuclear reactor generated heat to electrical energy upon a nuclear reactor system shutdown event comprises:

at least one thermoelectric device sized to at least partially match the heat rejection of the at least one thermoelectric device with at least a portion of the heat produced by the nuclear reactor for converting nuclear reactor generated heat to electrical energy upon a nuclear reactor system shutdown event.

176. The system of claim 174, wherein the at least one thermoelectric device sized to meet at least one selected operational requirement of the nuclear reactor system for converting nuclear reactor generated heat to electrical energy upon a nuclear reactor system shutdown event comprises:

at least one thermoelectric device sized to at least partially match the power requirements of at least one selected operation system for converting nuclear reactor generated heat to electrical energy upon a nuclear reactor system shutdown event.

177. The system of claim 176, wherein the at least one thermoelectric device sized to at least partially match the power requirements of at least one selected operation system for converting nuclear reactor generated heat to electrical energy upon a nuclear reactor system shutdown event comprises:

at least one thermoelectric device sized to match the power requirements of at least one mechanical pump for converting nuclear reactor generated heat to electrical energy upon a nuclear reactor system shutdown event.

178. The system of claim 130, further comprising:

at least one substance or at least one device for substantially optimizing a thermal conduction between a portion of at least one nuclear reactor system and a portion of at least one thermoelectric device.

179. The system of claim 130, further comprising:

regulation circuitry for protecting at least one thermoelectric device.

180. The system of claim 179, wherein the regulation circuitry for protecting at least one thermoelectric device comprises:

bypass circuitry for protecting at least one thermoelectric device.

181. The system of claim 180, wherein the bypass circuitry for protecting at least one thermoelectric device comprises:

bypass circuitry configured to electrically bypass the at least one thermoelectric device for protecting at least one thermoelectric device.

182. The system of claim 181, wherein the bypass circuitry configured to electrically bypass the at least one thermoelectric device for protecting at least one thermoelectric device comprises:

at least one electromagnetic relay system, at least one solid state relay system, at least one transistor, at least one microprocessor controlled relay system, at least one microprocessor controlled relay system programmed to respond to at least one external parameter, or at least one microprocessor controlled relay system programmed to respond to at least one internal parameter.

183. The system of claim 130, further comprising:

at least one reserve thermoelectric device and reserve actuation circuitry configured to selectively couple the at least one reserve thermoelectric device to the at least one thermoelectric device for selectively augmenting at least one thermoelectric device.

184. The system of claim 183, wherein the at least one reserve thermoelectric device and reserve actuation circuitry configured to selectively couple the at least one reserve thermoelectric device to the at least one thermoelectric device for selectively augmenting at least one thermoelectric device comprises:

at least one relay system, at least one electromagnetic relay system, at least one solid state relay system, at least one transistor, at least one microprocessor controlled relay system, at least one microprocessor controlled relay system programmed to respond to at least one external parameter, or at least one microprocessor controlled relay system to respond to at least one internal parameter to the at least one thermoelectric device.

185. The system of claim 130, further comprising:

power management circuitry for modifying at least one thermoelectric device output.

186. The system of claim 185, wherein the power management circuitry for modifying at least one thermoelectric device output comprises:

voltage regulation circuitry for modifying at least one thermoelectric device output.