[go: up one dir, main page]

WO2012125040A1 - Method for powering a nuclear reactor's cooling pumps and other equipment by using the energy in the reactor's cooling water to power hot gas engines / stirling engines - Google Patents

Method for powering a nuclear reactor's cooling pumps and other equipment by using the energy in the reactor's cooling water to power hot gas engines / stirling engines Download PDF

Info

Publication number
WO2012125040A1
WO2012125040A1 PCT/NO2012/000026 NO2012000026W WO2012125040A1 WO 2012125040 A1 WO2012125040 A1 WO 2012125040A1 NO 2012000026 W NO2012000026 W NO 2012000026W WO 2012125040 A1 WO2012125040 A1 WO 2012125040A1
Authority
WO
WIPO (PCT)
Prior art keywords
engines
cooling
hot gas
reactor
nuclear reactor
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Ceased
Application number
PCT/NO2012/000026
Other languages
French (fr)
Inventor
Ola Heggen
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Individual
Original Assignee
Individual
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Individual filed Critical Individual
Publication of WO2012125040A1 publication Critical patent/WO2012125040A1/en
Anticipated expiration legal-status Critical
Ceased legal-status Critical Current

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/18—Emergency cooling arrangements; Removing shut-down heat
    • G21C15/182—Emergency cooling arrangements; Removing shut-down heat comprising powered means, e.g. pumps
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D1/00—Details of nuclear power plant
    • G21D1/02—Arrangements of auxiliary equipment
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D1/00—Details of nuclear power plant
    • G21D1/04—Pumping arrangements
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

Definitions

  • Disturbances in the operation of a nuclear reactor may occur when extra pumping capacity or emergency cooling systems are required. These systems are generally driven by standby generators which start automatically. But emergency diesel generators may also suffer disturbances, and not be available in unpredictable circumstances such as earthquakes and etc.
  • a possible solution is to use one or more Hot gas engines/Stirling engines which obtain energy from the reactor's cooling water.
  • the advantage of the current invention is that the heat which has to be removed from the nuclear reactor is utilized to propel one or more Hot gas engines/Stirling engines which can drive essential cooling systems and other nuclear reactor's equipment.
  • the invention concerns the use of heat generated in the nuclear reactor to drive one or more Hot gas engines/Stirling engines, which in turn can directly or indirectly drive pumps and other essential equipment to provide and maintain cooling to a nuclear reactor, in particular at disturbances in the operation.
  • Hot gas engine/Stirling engine The advantage of employing a Hot gas engine/Stirling engine is that the larger the temperature difference between the Hot gas engine/Stirling engine's hot and cold side - the more powerful the engine is. Therefore when temperature rises in a nuclear reactor, one or more Hot gas engines/Stirling engines could drive pumps and other equipment, provided that a cooling reservoir for Hot gas
  • Such a reservoir can be water/ sea/ air/ ground.
  • Figure 1 is an outline of embodiment of the invention where the method is exemplified with a cooling cycle connected to a Hot gas engine/Stirling engine.
  • Figure 2 is an outline of a Hot gas engine/Stirling engine
  • Nuclear reactor inlet and outlet for water/coolant.
  • Cooling reservoir for Hot gas engine/Stirling engine Cooling reservoir for Hot gas engine/Stirling engine.

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Separation By Low-Temperature Treatments (AREA)
  • Engine Equipment That Uses Special Cycles (AREA)

Abstract

The invention concerns a method for powering cooling pumps (9) of a nuclear reactor (1) by using the energy in the reactor's cooling water (2) for powering one or more hot gas engines / Stirling engines (5). The method uses the heat in the coolant (2) of a nuclear reactor (1), wherein the reactor's coolant (2) is directed through a reactor's outlet (4a,b,...) into one or more hot gas engines / Stirling engines (5). The coolant (2) is directed through the engine's inlet (11a) onto ist hot side (14). The coolant (2) heats the hot side of the hot gas engines / Stirling engines (14) before it reaches the outlet (1 lb). From there the coolant (2) is normally directed to the pump (9) which pumps the coolant (2) to the cooling tower (10), where the coolant (2) is cooled before being directed back into the nuclear reactor (1) through the inlet (4a,b,...). Hot gas engines / Stirling engines (5) will drive pumps (9) and other equipment directly or indirectly by means of a generator (7) and a motor (8). Hot gas engines / Stirling engines (5) require a cooling reservoir (6) to cool its cold side (13). Such a reservoir (6) can be water, air, sea, ground or similar.

Description

METHOD FOR POWERING A NUCLEAR REACTOR'S COOLING PUMPS AND OTHER EQUIPMENT BY USING THE ENERGY IN THE REACTOR'S COOLING WATER TO POWER HOT
GAS ENGINES / STIRLING ENGINES
Method for propulsion of nuclear reactor's cooling pumps and other equipment by using the energy in the reactor's cooling water to propel Hot gas engines/Stirling engines.
Known technology:
Disturbances in the operation of a nuclear reactor may occur when extra pumping capacity or emergency cooling systems are required. These systems are generally driven by standby generators which start automatically. But emergency diesel generators may also suffer disturbances, and not be available in unpredictable circumstances such as earthquakes and etc.
A possible solution is to use one or more Hot gas engines/Stirling engines which obtain energy from the reactor's cooling water.
Among known technologies is "Heat Economiser" of 1816, English patent by Robert Stirling on Stirling engine and Hot gas engine.
The advantage of the current invention is that the heat which has to be removed from the nuclear reactor is utilized to propel one or more Hot gas engines/Stirling engines which can drive essential cooling systems and other nuclear reactor's equipment.
Short description of the invention:
The invention concerns the use of heat generated in the nuclear reactor to drive one or more Hot gas engines/Stirling engines, which in turn can directly or indirectly drive pumps and other essential equipment to provide and maintain cooling to a nuclear reactor, in particular at disturbances in the operation.
The advantage of employing a Hot gas engine/Stirling engine is that the larger the temperature difference between the Hot gas engine/Stirling engine's hot and cold side - the more powerful the engine is. Therefore when temperature rises in a nuclear reactor, one or more Hot gas engines/Stirling engines could drive pumps and other equipment, provided that a cooling reservoir for Hot gas
engines/Stirling engines is available. Such a reservoir can be water/ sea/ air/ ground.
This method is less effective when applied to a nuclear reactor in normal operation because Hot gas engines/Stirling engines will as well be functioning as cooling elements with a relatively high cooling effect in relation to the mechanical work produced. Description of figures:
Figure 1 is an outline of embodiment of the invention where the method is exemplified with a cooling cycle connected to a Hot gas engine/Stirling engine.
Figure 2 is an outline of a Hot gas engine/Stirling engine
Detailed description of the invention:
1 Nuclear reactor. Reactor's water/coolant. Reactor core.
Nuclear reactor's inlet and outlet for water/coolant.
Hot gas engine/Stirling engine.
Cooling reservoir for Hot gas engine/Stirling engine.
Generator.
Motor.
Cooling pump.
10) Cooling tower.
11) Inlet and outlet for reactor's cooling water.
12) Insulation between the hot and the cold side of a Hot gas engine.
13) Hot gas engine's cold side.
14) Hot gas engine's hot side.
15) Hot gas engine's displacer and piston rod.
16) Hot gas engine's power piston and piston rod.
17) Hot gas engine's crank shaft.
18) Hot gas engine's flywheel/power take off.

Claims

Claims:
1. Method for propulsion of nuclear reactor's cooling pumps and other
equipment by using the energy in the reactor's cooling water to propel Hot gas engines/Stirling engines, characterized in that the excess heat generated in the nuclear reactor (1) is used as energy to propel one or more Hot gas engines/Stirling engines (5), which in turn directly or indirectly drive cooling pumps (9) and other equipment required to provide cooling to the nuclear reactor.
2. Method for propulsion of nuclear reactor's cooling pumps and other
equipment by using the energy in the reactor's cooling water to propel Hot gas engines/Stirling engines of claim 1, characterized in that one or more heat sinks (6) are used for cooling of the cold side of Hot gas engines/Stirling engines (13).
3. Method for propulsion of nuclear reactor's cooling pumps and other
equipment by using the energy in the reactor's cooling water to propel Hot gas engines/Stirling engines of claim 1, characterized in that when using this method, depending on nuclear reactor's operating conditions it can also be necessary to use more cooling systems based on various energy sources.
4. Method for propulsion of nuclear reactor's cooling pumps and other
equipment by using the energy in the reactor's cooling water to propel Hot gas engines/Stirling engines of claim 1 and 3, characterized in that when using this method, it can be necessary to have a cooling system additionally, either separated or connected with other cooling systems, to transport coolant (2) from the nuclear reactor (1) first to one or several Hot gas engines/Stirling engines (5) before it is sent for further cooling, which is for the reason that it can be disadvantageous to use Hot gas
engines/Stirling engines (5) in normal operation of the nuclear reactor (1) since Hot gas engines/Stirling engines (5) are cooling elements
themselves.
PCT/NO2012/000026 2011-03-14 2012-03-09 Method for powering a nuclear reactor's cooling pumps and other equipment by using the energy in the reactor's cooling water to power hot gas engines / stirling engines Ceased WO2012125040A1 (en)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
NO20110388A NO20110388A1 (en) 2011-03-14 2011-03-14 Method for operating coolant pumps and other equipment for nuclear power reactors by utilizing the energy in the reactor's coolant for operating Hot Gas Engines / Sterling Engines.
NO20110388 2011-03-14

Publications (1)

Publication Number Publication Date
WO2012125040A1 true WO2012125040A1 (en) 2012-09-20

Family

ID=46830933

Family Applications (1)

Application Number Title Priority Date Filing Date
PCT/NO2012/000026 Ceased WO2012125040A1 (en) 2011-03-14 2012-03-09 Method for powering a nuclear reactor's cooling pumps and other equipment by using the energy in the reactor's cooling water to power hot gas engines / stirling engines

Country Status (2)

Country Link
NO (1) NO20110388A1 (en)
WO (1) WO2012125040A1 (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN110648771A (en) * 2019-10-09 2020-01-03 合肥本构智能科技有限公司 Passive Circulation Cooling System of Nuclear Power Reactor Cavity Based on Stirling Engine
CN117727474A (en) * 2023-11-27 2024-03-19 中核霞浦核电有限公司 Passive residual heat removal system of liquid metal cooling reactor

Citations (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3627633A (en) * 1967-11-06 1971-12-14 Teledyne Inc Unique metal hydride controlled reactors
US4057465A (en) * 1975-08-08 1977-11-08 Westinghouse Electric Corporation Nuclear reactor auxiliary heat removal system
US4457889A (en) * 1980-07-25 1984-07-03 Framatome Process and device for emergency cooling of a nuclear reactor
US5108695A (en) * 1991-02-25 1992-04-28 Westinghouse Electric Corp. Ventilating system for an emergency feedwater enclosure in a nuclear power plant
KR20090105540A (en) * 2008-04-03 2009-10-07 한국과학기술원 Nuclear Power Generation System Using Stirling Engine and Its Generation Method
US20110283701A1 (en) * 2011-08-07 2011-11-24 Shahriar Eftekharzadeh Self Powered Cooling

Patent Citations (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3627633A (en) * 1967-11-06 1971-12-14 Teledyne Inc Unique metal hydride controlled reactors
US4057465A (en) * 1975-08-08 1977-11-08 Westinghouse Electric Corporation Nuclear reactor auxiliary heat removal system
US4457889A (en) * 1980-07-25 1984-07-03 Framatome Process and device for emergency cooling of a nuclear reactor
US5108695A (en) * 1991-02-25 1992-04-28 Westinghouse Electric Corp. Ventilating system for an emergency feedwater enclosure in a nuclear power plant
KR20090105540A (en) * 2008-04-03 2009-10-07 한국과학기술원 Nuclear Power Generation System Using Stirling Engine and Its Generation Method
US20110283701A1 (en) * 2011-08-07 2011-11-24 Shahriar Eftekharzadeh Self Powered Cooling

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN110648771A (en) * 2019-10-09 2020-01-03 合肥本构智能科技有限公司 Passive Circulation Cooling System of Nuclear Power Reactor Cavity Based on Stirling Engine
CN117727474A (en) * 2023-11-27 2024-03-19 中核霞浦核电有限公司 Passive residual heat removal system of liquid metal cooling reactor

Also Published As

Publication number Publication date
NO20110388A1 (en) 2012-09-17

Similar Documents

Publication Publication Date Title
EP2954176B1 (en) Apparatus for heating an expansion machine of a waste heat recovery apparatus
WO2013019589A3 (en) Power generation from decay heat for spent nuclear fuel pool colling and monitoring
KR101814878B1 (en) Ship propulsion system and method of operation of ship and ship propulsion system
CA3010112C (en) Process and system for extracting useful work or electricity from thermal sources
US20120023942A1 (en) Method for increasing the net electric power of solar thermal power stations
KR101613228B1 (en) Waste Heat Recovery Unit for a Ship and Method for Recoverying Waste Heat
KR101399428B1 (en) Safety system of orc generation system
WO2018138314A1 (en) Waste heat recovery system
CN105201622A (en) Cooling and lubricating system of marine diesel engine
WO2012125040A1 (en) Method for powering a nuclear reactor's cooling pumps and other equipment by using the energy in the reactor's cooling water to power hot gas engines / stirling engines
JP2010077856A (en) Emergency diesel generator facility and its operation method
KR101403622B1 (en) Waste heat recovery system for ship that can remove dissolved oxygen by minimizing steam consumption
US11274629B2 (en) System and method for energy recovery in industrial faciliiies
KR20170135066A (en) Supercritical Carbon Dioxide Power Generation System and Ship having the same
KR20170138267A (en) System for recycling wasted heat of vessel
KR102492650B1 (en) Complex power generating system and ship having the same
CN211642568U (en) Power circulation and propulsion system and underwater vehicle
US20150059663A1 (en) Cooling system for machine system
EP2816215A1 (en) Energy conversion system
US7930889B1 (en) Gas or steam turbine with inlet air cooling
JP2013007324A (en) Gas turbine, and gas turbine combined cycle power generation equipment
CN104106201A (en) Machine for recovering energy from a waste heat flow of an internal combustion engine in a vehicle having a working medium circuit
CA2696046A1 (en) System to provide heat using an engine
CN110758697A (en) Power cycle and propulsion system and underwater vehicle
KR102492649B1 (en) Complex power generating system and ship having the same

Legal Events

Date Code Title Description
121 Ep: the epo has been informed by wipo that ep was designated in this application

Ref document number: 12757487

Country of ref document: EP

Kind code of ref document: A1

NENP Non-entry into the national phase

Ref country code: DE

122 Ep: pct application non-entry in european phase

Ref document number: 12757487

Country of ref document: EP

Kind code of ref document: A1