US20080298534A1 - Nuclear Plant with a Pebble Bed Nuclear Reactor - Google Patents

Nuclear Plant with a Pebble Bed Nuclear Reactor Download PDF

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Publication number
US20080298534A1
US20080298534A1 US11/996,947 US99694707A US2008298534A1 US 20080298534 A1 US20080298534 A1 US 20080298534A1 US 99694707 A US99694707 A US 99694707A US 2008298534 A1 US2008298534 A1 US 2008298534A1
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United States
Prior art keywords
sphere
reactor
inlet
outlet
gas
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.)
Abandoned
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US11/996,947
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English (en)
Inventor
Holger Gerhard Clemens Finken
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.)
Pebble Bed Modular Reactor Pty Ltd
Original Assignee
Pebble Bed Modular Reactor Pty Ltd
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 Pebble Bed Modular Reactor Pty Ltd filed Critical Pebble Bed Modular Reactor Pty Ltd
Assigned to PEBBLE BED MODULAR REACTOR (PROPRIETARY) LIMITED reassignment PEBBLE BED MODULAR REACTOR (PROPRIETARY) LIMITED ASSIGNMENT OF ASSIGNORS INTEREST (SEE DOCUMENT FOR DETAILS). Assignors: FINKEN, HOLGER GERHARD CLEMENS
Publication of US20080298534A1 publication Critical patent/US20080298534A1/en
Abandoned legal-status Critical Current

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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C1/00—Reactor types
    • G21C1/04—Thermal reactors ; Epithermal reactors
    • G21C1/06—Heterogeneous reactors, i.e. in which fuel and moderator are separated
    • G21C1/07—Pebble-bed reactors; Reactors with granular fuel
    • 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

  • THIS INVENTION relates to nuclear power. More particularly, it relates to a nuclear plant. It further relates to a method of operating a nuclear plant.
  • a reactor of this type is generally known as a pebble bed reactor.
  • a pebble bed reactor it is known to operate a multi-pass fuelling scheme in which fuel spheres are passed through a core of the reactor more than once in order to optimise burn-up of fuel.
  • a multi-pass fuelling scheme is believed to provide for a more uniform distribution of burn-up within the core and thereby flattens the axial neutron flux profile and maximises thermal power output of the reactor core.
  • the fuel spheres and, if applicable, moderator spheres are conveyed to an inlet in a reactor or a storage vessel in a sphere flow path, partly by gravity but predominantly using gas flow.
  • spheres will be considered to be broad enough to include both fuel spheres and, where appropriate, moderator spheres.
  • the spheres are fed into the reactor through one or more sphere inlets at or adjacent the top thereof, from where they fall onto an upper surface of a bed or spheres in the reactor core.
  • the spheres are drawn from the reactor vessel at or adjacent the bottom thereof through one or more sphere outlets.
  • the spheres are conveyed between the or each sphere outlet and the or each sphere inlet by a fuel handling and storage system.
  • the fuel handling and storage system includes, inter alia, a network of pipes connecting the sphere outlets and sphere inlets in communication and a blower for causing gas flow through the network of pipes capable of entraining the spheres and transporting them through the pipes.
  • An example of a fuel handling and storage system of this type is set out in Applicant's earlier application US 2003/0227994 which is incorporated herein by reference.
  • the reactor coolant typically helium
  • the mass of working fluid in the main power system can be varied. This is achieved by using a helium inventory control system which includes one or more helium storage tanks which are connectable in flow communication with the main power system either to introduce helium into the main power system to increase power generated in the main power system or to remove helium from the main power system to decrease the power generated by the main power system.
  • a helium inventory control system which includes one or more helium storage tanks which are connectable in flow communication with the main power system either to introduce helium into the main power system to increase power generated in the main power system or to remove helium from the main power system to decrease the power generated by the main power system.
  • Rapid pressure fluctuations can also occur during a faulted operation of the main power system, e.g. as a result of a turbine trip or failure.
  • the coolant gas is also used as the conveying medium in the fuel handling and storage system. Further, whilst the fuel handling and storage system must be connected to the reactor in order to permit spheres to be conveyed from the reactor outlet to the reactor inlet, it is undesirable to expose the components of the fuel handling and storage system to the high temperatures and pressure fluctuations of the main power system.
  • a nuclear plant which includes
  • a pebble bed nuclear reactor having at least one sphere inlet at or towards an upper end thereof and at least one sphere outlet at or towards a lower end thereof;
  • This arrangement results in a gas leak flow from the fuel handling and storage system to the reactor which inhibits the ingress of hot gas from the reactor into the fuel handling and storage system.
  • the plant may include damping means configured to permit the passage of spheres between the reactor and the fuel handling and storage system and to dampen the transmission of pressure fluctuations in coolant of the reactor to the fuel handling and storage system.
  • the sphere flow path pressurising means may include a blower having an inlet and an outlet, the blower outlet being connected to the sphere flow path at a gas inlet and the blower inlet being connected to the sphere flow path at a gas outlet, the gas inlet being positioned at a level which is lower than the level of the sphere inlet of the sphere flow path such that spheres entering the sphere flow path from the reactor will move under the influence of gravity to the gas inlet where they will be entrained in a gas stream flowing through the sphere flow path and conveyed away from the gas inlet.
  • the plant may include a top flow restricting indexer positioned, relative to the direction of movement of the spheres, upstream of the sphere inlet of the reactor and a bottom flow restricting indexer positioned downstream of the sphere outlet of the reactor.
  • the flow restricting indexers function as the damping means.
  • the top flow restricting indexer may be positioned between the gas outlet of the sphere flow path and the sphere inlet of the reactor and the bottom flow restricting indexer may be positioned between the sphere outlet of the reactor and the gas inlet of the sphere flow path.
  • the plant may include
  • a closed loop main power system which includes, in addition to the nuclear reactor, in series, at least one turbine and at least one compressor;
  • a feed line for feeding gas from the main power system to the fuel handling and storage system to replace gas which flows from the fuel handling and storage system into the reactor.
  • the main power system may further include a recuperator having a hot or low pressure side connected between the at least one turbine and the at least one compressor, and a cold or high pressure side connected between the at least one compressor and a gas or working fluid inlet of the reactor, the feed line leading from the main power system from a position between the at least one compressor and the cold side of the recuperator and being connected to the fuel handling and storage system between the gas outlet and the inlet of the blower.
  • a recuperator having a hot or low pressure side connected between the at least one turbine and the at least one compressor, and a cold or high pressure side connected between the at least one compressor and a gas or working fluid inlet of the reactor, the feed line leading from the main power system from a position between the at least one compressor and the cold side of the recuperator and being connected to the fuel handling and storage system between the gas outlet and the inlet of the blower.
  • a nuclear plant which includes
  • a pebble bed nuclear reactor having at least one sphere inlet at or towards an upper end thereof and at least one sphere outlet at or towards a lower end thereof;
  • a fuel handling and storage system which includes sphere flow path defining means defining a sphere flow path having a
  • the damping means may include a top flow restricting indexer positioned, relative to the direction of movement of the spheres, upstream of the sphere inlet of the reactor and a bottom flow restricting indexer positioned downstream of the sphere outlet of the reactor.
  • a method of operating a nuclear plant having a pebble bed nuclear reactor having a sphere outlet and a sphere inlet and a fuel handling and storage system for conveying spheres from the sphere outlet of the reactor to the sphere inlet of the reactor which method includes the step of pressurising the fuel handling and storage system to create a leak flow from the fuel handling and storage system to the reactor.
  • the leak flow from the fuel handling and storage system to the reactor may be through both the sphere outlet and sphere inlet of the reactor.
  • the nuclear plant may include a closed loop main power system of which the reactor forms part and the method may include feeding gas from the main power system into the fuel handling and storage system to replace gas leaked from the fuel handling and storage system into the reactor.
  • the gas may be fed from the main power system from a position where the gas in the main power system is at maximum pressure.
  • reference numeral 10 refers generally to a nuclear plant in accordance with the invention.
  • the plant 10 includes a closed loop main power system, generally indicated by reference numeral 12 and a fuel handling and storage system, generally indicated by reference numeral 14 .
  • the main power system 12 includes a high temperature gas cooled pebble bed nuclear reactor 16 having, a working fluid or coolant inlet 18 and outlet 20 and a sphere inlet 22 and sphere outlet 24 .
  • the plant 10 further includes a turbine 26 , a recuperator 28 , a pre-cooler 30 , a low pressure compressor 32 , an inter-cooler 34 , a high pressure compressor 36 and an electrical generator 38 .
  • the generator 38 and compressors 32 , 36 are mounted on a common shaft 40 to which the turbine 26 is drivingly connected.
  • the turbine 26 has an inlet 26 . 1 and an outlet 26 . 2 .
  • the inlet 26 . 1 is in flow communication with the outlet 20 .
  • the recuperator 28 has a hot or low pressure side 42 and a cold or high pressure side 44 .
  • the low pressure side 42 has an inlet 42 . 1 and an outlet 42 . 2 .
  • the inlet 42 . 1 is connected in flow communication with the outlet 26 . 2 .
  • the pre-cooler 30 has an inlet 30 . 1 and an outlet 30 . 2 .
  • the outlet 42 . 2 is in flow communication with the inlet 30 . 1 .
  • the low pressure compressor 32 has an inlet 32 . 1 and an outlet 32 . 2 .
  • the outlet 30 . 2 is in flow communication with the inlet 32 . 1 .
  • the inter-cooler 34 has an inlet 34 . 1 and an outlet 34 . 2 .
  • the outlet 32 . 2 is in flow communication with the inlet 34 . 1 .
  • the high pressure compressor 36 has an inlet 36 . 1 and an outlet 36 . 2 .
  • the outlet 34 . 2 of the inter-cooler 34 is in flow communication with the inlet 36 . 1 .
  • the high pressure side 44 of the recuperator 28 has an inlet 44 . 1 and an outlet 44 . 2 .
  • the outlet 36 . 2 of the high pressure compressor 36 is connected to the inlet 44 . 1 of the high pressure side 44 of the recuperator.
  • the outlet 44 . 2 of the high pressure side of the recuperator 44 is connected to the inlet 18 .
  • the fuel handling and storage system 14 includes a sphere flow path defining means defining a sphere flow path 50 having an inlet which is connected to the sphere outlet 24 of the reactor 16 and an outlet which is connected to the sphere inlet 22 of the reactor 16 .
  • the system 14 further includes a blower 52 which has an inlet 54 and an outlet 56 .
  • the outlet 56 is connected in flow communication with the sphere flow path 50 at a gas inlet indicated by reference numeral 58 .
  • the inlet 54 of the blower 52 is connected in flow communication with the sphere flow path 50 at a gas outlet 60 .
  • Mounted in series with the blower 52 are a heat exchanger 62 and a filter 64 .
  • the gas inlet 58 is positioned at a level which is lower than the level of the sphere outlet 24 .
  • a bottom flow restricting indexer 66 is provided in the sphere flow path 50 at a position between the sphere outlet 24 and the gas inlet 58 .
  • a top flow restricting indexer 68 is positioned in the sphere flow path 50 at a position between the gas outlet 60 and the sphere inlet 22 .
  • a feed line 70 extends from a high pressure point of the main power system 12 at a position between the outlet 36 . 2 of the high pressure compressor 36 and the inlet 44 . 1 of the high pressure side 44 of the recuperator 28 .
  • a valve arrangement, generally indicated by reference numeral 72 is provided in the feed line 70 .
  • the valve arrangement 72 includes a non-return valve.
  • working fluid or coolant typically helium
  • working fluid or coolant is fed into the reactor 16 through the inlet 18 .
  • the heated working fluid exits the reactor through the outlet 20 and drives the turbine 26 which in turn drives the compressors 32 , 36 and the generator 38 .
  • the working fluid is cooled in the recuperator 28 and the pre-cooler 30 prior to entering the low pressure compressor 32 where it is compressed.
  • the working fluid is then cooled in the inter-cooler 34 before entering the high pressure compressor 36 from where it is fed to the low pressure side of the recuperator 28 and is heated by gas passing through the low pressure side 42 of the recuperator, before being returned to the reactor 16 .
  • Control of the power generated in the main power system 12 is achieved, inter alia, by making use of a helium inventory control system which controls the mass of working fluid in the main power system 12 .
  • the blower 52 causes a stream of gas to flow through the sphere flow path 50 between the gas inlet 58 and the gas outlet 60 .
  • the fuel handling and storage system is arranged such that the pressure within the sphere flow path 50 is higher than that at the sphere inlet 22 and sphere outlet 24 . Accordingly, there is a leak flow of gas from the sphere flow path 50 into the reactor 16 through the sphere inlet 22 and sphere outlet 24 . It will be appreciated that helium is lost from the fuel handling and storage system 14 into the reactor 16 on a continuous basis. This loss of helium is made up by helium flowing through the feed line 70 into the fuel handling and storage system 14 .
  • the helium is drawn from the main power system 12 at a location which corresponds to the highest pressure of the main power system, i.e. where the pressure is higher than at the sphere inlet 22 and sphere outlet 24 , and also at a position where the helium is at a relatively low temperature, typically of the order of 100° C.
  • the bottom flow restricting indexer 66 is arranged to permit the leak flow of helium into the reactor and at the same time to permit the spheres 74 to move through the sphere flow path 50 in the opposite direction.
  • One possible sphere route is that the spheres 74 are then fed through the top flow restricting indexer 68 and the sphere inlet 22 into the reactor.
  • the fuel handling and storage system 14 will typically incorporate sorting and management functions, e.g. for checking the integrity of the fuel elements and for removing damaged fuel elements. Further, the fuel handling and storage system will typically incorporate means for determining whether or not a fuel element is suitable for a further pass through the reactor and thereby separating spent fuel elements from used fuel elements which are still capable of producing useful energy. The details of the fuel handling and storage system are not necessary for an understanding of the principle of the invention and hence, are not described in detail
  • a plant in accordance with the invention will have the advantage that the leak flow of helium from the fuel handling and storage system 14 into the nuclear reactor will inhibit the ingress of high temperature gas from the reactor to the fuel handling and storage system.
  • the provision of the bottom flow restricting indexer 66 and top flow restricting indexer 68 permit the fuel handling and storage system to operate at relatively low temperatures thereby avoiding the need to design the components of the fuel handling and storage system to operate at high temperatures with a substantial cost saving and an increase in reliability.
  • the pressure of helium in the fuel handling and storage system will remain relatively stable or change slowly thereby reducing the risk of damage to components of the fuel handling and storage system owing to pressure fluctuations in the main power system.

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)
  • Fuel Cell (AREA)
  • Filling Or Discharging Of Gas Storage Vessels (AREA)
US11/996,947 2006-02-09 2007-02-08 Nuclear Plant with a Pebble Bed Nuclear Reactor Abandoned US20080298534A1 (en)

Applications Claiming Priority (3)

Application Number Priority Date Filing Date Title
ZA200601183 2006-02-09
ZA2006/01183 2006-02-09
PCT/IB2007/050413 WO2007091220A1 (en) 2006-02-09 2007-02-08 Nuclear plant with a pebble bed nuclear reactor

Related Parent Applications (1)

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PCT/IB2007/050413 A-371-Of-International WO2007091220A1 (en) 2006-02-09 2007-02-08 Nuclear plant with a pebble bed nuclear reactor

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US13/418,298 Division US8817940B2 (en) 2006-02-09 2012-03-12 Nuclear plant with a pebble bed nuclear reactor

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US20080298534A1 true US20080298534A1 (en) 2008-12-04

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US13/418,298 Active US8817940B2 (en) 2006-02-09 2012-03-12 Nuclear plant with a pebble bed nuclear reactor

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Country Status (8)

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US (2) US20080298534A1 (ja)
EP (1) EP1982336B1 (ja)
JP (1) JP5389452B2 (ja)
KR (1) KR101461678B1 (ja)
CN (1) CN101331555B (ja)
CA (1) CA2625618C (ja)
WO (1) WO2007091220A1 (ja)
ZA (1) ZA200711168B (ja)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN101814325A (zh) * 2010-04-09 2010-08-25 吕应中 在任何功率下长期自动运行生产高温核能的方法
US20130287162A1 (en) * 2009-11-03 2013-10-31 Korea Advanced Institute Of Science And Technology Integrated process for water-hydrogen-electricity nuclear gas-cooled reactor

Families Citing this family (5)

* Cited by examiner, † Cited by third party
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FR2956773B1 (fr) * 2010-02-24 2012-03-23 Commissariat Energie Atomique Installation de production d'energie a partir d'un reacteur nucleaire rapide a gaz
CN103578575B (zh) * 2012-07-25 2016-08-31 李正蔚 球形燃料反应堆
US10522255B2 (en) 2015-02-19 2019-12-31 X-Energy, Llc Nuclear fuel pebble and method of manufacturing the same
US9793010B2 (en) 2015-02-19 2017-10-17 X-Energy, Llc Nuclear fuel pebble and method of manufacturing the same
US11508488B2 (en) 2020-09-10 2022-11-22 Battelle Energy Alliance, Llc Heat transfer systems for nuclear reactor cores, and related systems

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US20060050835A1 (en) * 2004-09-03 2006-03-09 Bazant Martin Z Bi-disperse pebble-bed nuclear reactor
US7403585B2 (en) * 2004-07-01 2008-07-22 Battelle Energy Alliance, Llc Optimally moderated nuclear fission reactor and fuel source therefor

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CN1439162A (zh) * 2000-06-29 2003-08-27 埃斯科姆公司 卵石床式核反应堆
EP1395995B1 (en) * 2001-05-23 2006-03-22 Pebble Bed Modular Reactor (Proprietary) Limited Method and device for slowing down spherical elements in a pebble bed nuclear reactor
WO2003043025A1 (en) * 2001-11-16 2003-05-22 Pebble Bed Modular Reactor (Proprietary) Limited Nuclear power plant with a gas cooled reactor
AU2003264779A1 (en) * 2002-10-25 2004-05-13 Pebble Bed Modular Reactor (Proprietary) Limited Flow control device

Patent Citations (12)

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Publication number Priority date Publication date Assignee Title
US2975116A (en) * 1946-10-08 1961-03-14 Daniels Farrington Neutronic reactor
US2959574A (en) * 1958-02-17 1960-11-08 American Cyanamid Co Water-soluble reaction composition of hydroxylamine with acrylamide-acrylonitrile copolymer
US4536296A (en) * 1980-02-14 1985-08-20 Societe Nationale Elf Aquitaine Drilling and completion muds useful at elevated temperatures
US4532046A (en) * 1982-11-24 1985-07-30 Societe Nationale Elf Aquitaine Method for hindering the scaling by waters
US4767540A (en) * 1987-02-11 1988-08-30 American Cyanamid Company Polymers containing hydroxamic acid groups for reduction of suspended solids in bayer process streams
US6262183B1 (en) * 1987-02-26 2001-07-17 Cytec Technology Corp. Hydroxamic acid polymers formed from primary amide polymers
US4810296A (en) * 1988-02-16 1989-03-07 American Cyanamid Company Hydroxamated polymers as additives for retarding the rate of set of hydraulic cement compositions
US4868248A (en) * 1989-03-22 1989-09-19 Nalco Chemical Company Polyhydroxyamic acid polymers from polyacrylic acids
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US20030227994A1 (en) * 2000-06-29 2003-12-11 Franco Curtolo Nuclear plant
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Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US20130287162A1 (en) * 2009-11-03 2013-10-31 Korea Advanced Institute Of Science And Technology Integrated process for water-hydrogen-electricity nuclear gas-cooled reactor
CN101814325A (zh) * 2010-04-09 2010-08-25 吕应中 在任何功率下长期自动运行生产高温核能的方法
CN101814325B (zh) * 2010-04-09 2012-09-26 吕应中 在任何功率下长期自动运行生产高温核能的方法

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Publication number Publication date
CA2625618A1 (en) 2007-08-16
EP1982336A1 (en) 2008-10-22
KR101461678B1 (ko) 2014-11-13
US8817940B2 (en) 2014-08-26
ZA200711168B (en) 2008-12-31
CN101331555A (zh) 2008-12-24
JP2009526218A (ja) 2009-07-16
EP1982336B1 (en) 2013-04-24
CA2625618C (en) 2015-04-14
CN101331555B (zh) 2012-04-18
US20120230458A1 (en) 2012-09-13
KR20080091751A (ko) 2008-10-14
WO2007091220A1 (en) 2007-08-16
JP5389452B2 (ja) 2014-01-15

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Legal Events

Date Code Title Description
AS Assignment

Owner name: PEBBLE BED MODULAR REACTOR (PROPRIETARY) LIMITED,

Free format text: ASSIGNMENT OF ASSIGNORS INTEREST;ASSIGNOR:FINKEN, HOLGER GERHARD CLEMENS;REEL/FRAME:020441/0324

Effective date: 20071005

STCB Information on status: application discontinuation

Free format text: ABANDONED -- FAILURE TO RESPOND TO AN OFFICE ACTION