[go: up one dir, main page]

WO2017105325A1 - Tige d'arrêt pour réacteurs nucléaires refroidis au plomb - Google Patents

Tige d'arrêt pour réacteurs nucléaires refroidis au plomb Download PDF

Info

Publication number
WO2017105325A1
WO2017105325A1 PCT/SE2016/051258 SE2016051258W WO2017105325A1 WO 2017105325 A1 WO2017105325 A1 WO 2017105325A1 SE 2016051258 W SE2016051258 W SE 2016051258W WO 2017105325 A1 WO2017105325 A1 WO 2017105325A1
Authority
WO
WIPO (PCT)
Prior art keywords
shutdown
shutdown rod
boron
lead
rod
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/SE2016/051258
Other languages
English (en)
Inventor
Janne Wallenius
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.)
Blykalla Reaktorer Stockholm AB
Original Assignee
Blykalla Reaktorer Stockholm AB
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 Blykalla Reaktorer Stockholm AB filed Critical Blykalla Reaktorer Stockholm AB
Priority to CN201680073929.4A priority Critical patent/CN108369826B/zh
Publication of WO2017105325A1 publication Critical patent/WO2017105325A1/fr
Anticipated expiration legal-status Critical
Ceased legal-status Critical Current

Links

Classifications

    • CCHEMISTRY; METALLURGY
    • C04CEMENTS; CONCRETE; ARTIFICIAL STONE; CERAMICS; REFRACTORIES
    • C04BLIME, MAGNESIA; SLAG; CEMENTS; COMPOSITIONS THEREOF, e.g. MORTARS, CONCRETE OR LIKE BUILDING MATERIALS; ARTIFICIAL STONE; CERAMICS; REFRACTORIES; TREATMENT OF NATURAL STONE
    • C04B35/00Shaped ceramic products characterised by their composition; Ceramics compositions; Processing powders of inorganic compounds preparatory to the manufacturing of ceramic products
    • C04B35/515Shaped ceramic products characterised by their composition; Ceramics compositions; Processing powders of inorganic compounds preparatory to the manufacturing of ceramic products based on non-oxide ceramics
    • C04B35/58Shaped ceramic products characterised by their composition; Ceramics compositions; Processing powders of inorganic compounds preparatory to the manufacturing of ceramic products based on non-oxide ceramics based on borides, nitrides, i.e. nitrides, oxynitrides, carbonitrides or oxycarbonitrides or silicides
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C7/00Control of nuclear reaction
    • G21C7/06Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
    • G21C7/08Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of solid control elements, e.g. control rods
    • G21C7/10Construction of control elements
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C7/00Control of nuclear reaction
    • G21C7/06Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
    • G21C7/24Selection of substances for use as neutron-absorbing material
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C9/00Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
    • G21C9/02Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse; Control elements having arrangements activated in an emergency
    • G21C9/027Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse; Control elements having arrangements activated in an emergency by fast movement of a solid, e.g. pebbles
    • CCHEMISTRY; METALLURGY
    • C04CEMENTS; CONCRETE; ARTIFICIAL STONE; CERAMICS; REFRACTORIES
    • C04BLIME, MAGNESIA; SLAG; CEMENTS; COMPOSITIONS THEREOF, e.g. MORTARS, CONCRETE OR LIKE BUILDING MATERIALS; ARTIFICIAL STONE; CERAMICS; REFRACTORIES; TREATMENT OF NATURAL STONE
    • C04B2235/00Aspects relating to ceramic starting mixtures or sintered ceramic products
    • C04B2235/70Aspects relating to sintered or melt-casted ceramic products
    • C04B2235/74Physical characteristics
    • C04B2235/77Density
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C1/00Reactor types
    • G21C1/02Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Definitions

  • This disclosure relates generally to the field of nuclear reactors and reactor safety, and concerns in particular a shutdown rod for lead-cooled and lead- bismuth cooled reactors.
  • shutdown rods containing a neutron absorbing material to allow the initiation of a controlled chain reaction of fission events, or to rapidly halt a controlled or uncontrolled chain of such events.
  • the shutdown rod is parked above or below the core, and when the need to halt the operation arises, the rod is vertically displaced until it absorbs a sufficient fraction of neutrons to make the reactor permanently sub-critical.
  • the insertion mechanism can be active, for example by using electrical motors, hydraulic devices or gas expansion systems. In case the insertion mechanism is based on the use of gravity, shutdown can be accomplished in a so called passive mode. For reasons of safety, the ability to shut down a reactor using passive mechanisms, such as gravity, is a desired feature in modern reactor design.
  • boron carbide, enriched boron carbide, cadmium, silver-indium-cadmium alloys or hafnium may be used as neutron absorbing material in shutdown rods.
  • shutdown rods comprising of boron carbide, europium oxides or europium hexaborides must be parked below the reactor core, if gravity (or rather buoyancy) is to be used to achieve passive shutdown, since the density of the aforementioned absorbers is much lower than that of the coolant. This location increases the height of the reactor vessel and complicates the design of the core support structure. Conversely, in order to place the shutdown rods above the core, the density of the absorbing material must be significantly higher than that of liquid lead or lead-bismuth, in order to achieve passive shutdown by means of gravity.
  • hafnium diboride based absorber materials are known in the art.
  • US 3,565,762 issued in 1971 , discloses an absorber element for nuclear reactors having a core of high-melting-point boride selected from the group which consists essentially of the diborides of zirconium, vanadium, hafnium and tantalum.
  • US 6,334,963, issued in 2002 discloses a neutron adsorbent material being a composite material comprising hafnium diboride and hafnium dioxide.
  • One object of the present disclosure is to provide an improved shutdown rod for liquid lead or lead-bismuth cooled reactors permitting passive shutdown after parking the shutdown rod above the core.
  • the rod consists essentially of a column of ceramic pellets enclosed in a steel cladding tube.
  • a first aspect relates to a shutdown rod for liquid lead or lead-bismuth cooled nuclear reactors comprising a column of ceramic boride absorber pellets enclosed in a steel cladding tube, wherein the cross sectional areal of the steel cladding tube comprises at least 10% of the cross sectional area of the shutdown rod and the average density of the shutdown rod at a temperature of 400°C is at least 10.7 g/cm 3 .
  • the ceramic absorber pellets consist essentially of ReB 2 (rhenium diboride).
  • the boron is enriched to at least 90% in boron-10.
  • the ceramic absorber pellets consist essentially of (W, Re)B 2 (tungsten-rhenium diboride) in the hexagonal ReBe 2 -phase.
  • the boron is enriched to at least 90% in boron-10.
  • the ceramic absorber pellets consist essentially of OsB2 (osmium diboride).
  • the boron is enriched to at least 90% in boron-10.
  • Figure 1 shows a schematic cross section of a shutdown rod or cartridge according to an embodiment.
  • the purpose of the present invention is to provide a shutdown rod for liquid lead or lead-bismuth cooled reactors permitting passive shutdown after parking the shutdown rod above the core.
  • the rod consists essentially of a column of ceramic boride absorber pellets enclosed in a steel cladding tube.
  • the cross sectional areal of the steel cladding tube comprises at least 10% of the cross sectional area of the shutdown rod.
  • a shutdown rod or cartridge (A) with absorption rods (B) according to an embodiment of the present disclosure is shown in Figure 1 .
  • the ceramic boride (1 ) is shown as dotted, and the steel cladding (2) as dashed surfaces in the figure.
  • the rod or cartridge is shown here having a hexagonal cross section, and comprising 37 absorption rods.
  • a rod or cartridge can have different shapes depending on the design of the reactor core.
  • a cartridge can also contain different numbers of absorption rods, and these can be arranged in different configurations, again provided that the overruling characteristics are fulfilled, i.e. a minimum density of 10.7 g/cm 3 at a temperature of about 400 °C is achieved.
  • the ceramic absorber pellet consists essentially of ReB 2 (rhenium diboride) and is manufactured with a porosity of less than 1 1 %.
  • the boron is enriched to at least 90% in boron-10.
  • the ceramic absorber pellet consists essentially of (W, Re)B 2 (tungsten-rhenium diboride) with a tungsten to rhenium molar ratio of 48% or less, and is manufactured with a porosity of less than 8 %.
  • the boron is enriched to at least 90% in boron-10.
  • the ceramic absorber pellet consists essentially of OsB 2 (osmium diboride) and is manufactured with a porosity of less than 12%.
  • the boron is enriched to at least 90% in boron-10.
  • the effective density of the shutdown rod including the steel cladding tube can be made higher than that of liquid lead or lead-bismuth at operating
  • the latter densities are approximately 10.6 g/cm 3 for liquid lead and 10.2 g/cm 3 for liquid lead-bismuth.
  • the theoretical densities (at zero porosity and room temperature) of ReB 2 , (W 0 . 4 8,Reo.52)B 2 or OsB 2 are 12.7 g/cm 3 , 12.3 g/cm 3 ; and 12.9 g/cm 3 ; respectively.
  • a requirement for the present applications is however that the density of the resulting shutdown rod is at least 10.7 g/cm 3 at a temperature of about 400 °C.
  • HfB 2 pellets with a porosity of less than 5% such pellets would have a density higher than liquid lead.
  • hafnium diboride is not a suitable material for the present use.
  • pure tungsten diboride exists only in the hexagonal AIB 2 phase, which is of considerably lower density than if it would exist in the high density hexagonal ReB 2 phase.
  • tungsten diboride must be dissolved into ReB 2 in order to obtain a sufficiently high density to serve the purpose of the present invention.
  • the solubility limit of tungsten diboride in rhenium diboride has been determined at 48% [Lech 2014].
  • a shutdown rod offers the possibility to construct shutdown systems, in particular passive shutdown systems with high density and excellent shutdown reactivity. This is important both in normal shutdown and in safety shutdown situations. Further advantages will become apparent to a skilled person upon study of the example and the appended claims.
  • the shutdown worth i.e. the reduction in reactivity
  • the shutdown reactivity pern, per cent mille resulting from inserting three shutdown elements was calculated for each of the preferred embodiments of the present invention, using the Serpent Monte-Carlo code (Serpent is a three-dimensional continuous-energy Monte Carlo reactor physics burnup calculation code, developed at VTT Technical Research Centre of Finland since 2004.
  • the publicly available Serpent 1 has been distributed by the OECD/NEA Data Bank and RSICC since 2009, and later versions of the code are available to registered users by request).

Landscapes

  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • Chemical & Material Sciences (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • Ceramic Engineering (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • Manufacturing & Machinery (AREA)
  • Materials Engineering (AREA)
  • Structural Engineering (AREA)
  • Organic Chemistry (AREA)
  • Ceramic Products (AREA)
  • Solid-Sorbent Or Filter-Aiding Compositions (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Aiming, Guidance, Guns With A Light Source, Armor, Camouflage, And Targets (AREA)

Abstract

L'invention concerne une tige d'arrêt pour réacteurs nucléaires refroidis par un liquide au plomb ou au plomb-bismuth comprenant une colonne de pastilles absorbantes de céramique de borure enfermées dans un tube de gainage en acier, la section transversale du tube de gainage en acier représentant au moins 10 % de la section transversale de la tige d'arrêt, et la densité moyenne de la tige d'arrêt à une température de 400 °C étant supérieure à 10,7 g/cm3.
PCT/SE2016/051258 2015-12-17 2016-12-14 Tige d'arrêt pour réacteurs nucléaires refroidis au plomb Ceased WO2017105325A1 (fr)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN201680073929.4A CN108369826B (zh) 2015-12-17 2016-12-14 一种铅冷反应堆停堆棒

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
SE1530195 2015-12-17
SE1530195-5 2015-12-17

Publications (1)

Publication Number Publication Date
WO2017105325A1 true WO2017105325A1 (fr) 2017-06-22

Family

ID=59057126

Family Applications (1)

Application Number Title Priority Date Filing Date
PCT/SE2016/051258 Ceased WO2017105325A1 (fr) 2015-12-17 2016-12-14 Tige d'arrêt pour réacteurs nucléaires refroidis au plomb

Country Status (2)

Country Link
CN (1) CN108369826B (fr)
WO (1) WO2017105325A1 (fr)

Citations (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3565762A (en) * 1966-02-26 1971-02-23 Kernforschungsanlage Juelich Absorber element for nuclear reactors
JPS5484811A (en) * 1977-12-19 1979-07-06 Tokushiyu Muki Zairiyou Kenkiy Neutron absorbing material and production thereof
US5273709A (en) * 1990-10-01 1993-12-28 Thermal Technology Inc. High neutron absorbing refractory compositions of matter and methods for their manufacture
US6334963B1 (en) * 1998-01-13 2002-01-01 Commisariat A L'energie Atomique Absorbent neutronic composite material and method for producing same
US20080050270A1 (en) * 2004-04-22 2008-02-28 Xiao-Guang Chen Neutron Absorption Effectiveness for Boron Content Aluminum Materials
JP2010107340A (ja) * 2008-10-30 2010-05-13 Kyocera Corp 中性子吸収体および原子力発電装置用制御棒

Family Cites Families (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN101734918B (zh) * 2009-12-18 2012-09-05 山东大学 一种致密富10b碳化硼陶瓷及其制备方法
CN103236276B (zh) * 2013-04-21 2016-12-28 中国科学院合肥物质科学研究院 一种用于液态重金属冷却反应堆的控制棒

Patent Citations (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3565762A (en) * 1966-02-26 1971-02-23 Kernforschungsanlage Juelich Absorber element for nuclear reactors
JPS5484811A (en) * 1977-12-19 1979-07-06 Tokushiyu Muki Zairiyou Kenkiy Neutron absorbing material and production thereof
US5273709A (en) * 1990-10-01 1993-12-28 Thermal Technology Inc. High neutron absorbing refractory compositions of matter and methods for their manufacture
US6334963B1 (en) * 1998-01-13 2002-01-01 Commisariat A L'energie Atomique Absorbent neutronic composite material and method for producing same
US20080050270A1 (en) * 2004-04-22 2008-02-28 Xiao-Guang Chen Neutron Absorption Effectiveness for Boron Content Aluminum Materials
JP2010107340A (ja) * 2008-10-30 2010-05-13 Kyocera Corp 中性子吸収体および原子力発電装置用制御棒

Non-Patent Citations (1)

* Cited by examiner, † Cited by third party
Title
PRISTAVITA, R. ET AL.: "Carbon Nanoparticle Production by Inductively Coupled Thermal Plasmas: Controlling the Thermal History of Particle Nucleation", PLASMA CHEMISTRY AND PLASMA PROCESSING, vol. 31, 2011, pages 851 - 866, XP019975397 *

Also Published As

Publication number Publication date
CN108369826B (zh) 2021-11-05
CN108369826A (zh) 2018-08-03

Similar Documents

Publication Publication Date Title
Sofu A review of inherent safety characteristics of metal alloy sodium-cooled fast reactor fuel against postulated accidents
CN101504872B (zh) 先进灰棒控制组件
CN103778972B (zh) 一种带轴向分区控制棒与重金属吸收体棒的控制棒组件
JP4739379B2 (ja) 軽水炉の炉心
CN110828002B (zh) 一种高价值控制棒中子吸收体材料
RU2013101773A (ru) Твердая промежуточная прокладка с открытой пористостью для ядерного управляющего стержня
CN108475545B (zh) 用于核反应堆的吸收棒组件和吸收棒
JP2013536426A (ja) 核燃料アセンブリの重大事故を軽減するための装置
CN101567226A (zh) 含有内部氢/氚吸纳体结构的燃料棒和组件
WO2018206234A1 (fr) Pastille de combustible nucléaire, tige de combustible et ensemble de combustible
US9378850B2 (en) Method for operating a nuclear reactor and use of a specific fuel rod cladding alloy in order to reduce damage caused by pellet/cladding interaction
WO2017105325A1 (fr) Tige d'arrêt pour réacteurs nucléaires refroidis au plomb
RU2524681C2 (ru) Твэл ядерного реактора
KR101668088B1 (ko) 원자로
van Rooijen Improving fuel cycle design and safety characteristics of a gas cooled fast reactor
Sundaram et al. Nuclear fuels and development of nuclear fuel elements
US20240371535A1 (en) Nuclear Reactor with Liquid Coolant and Solid Fuel Assemblies, Integrating a System of Evacuation of the Nominal Power with Liquid Metal Bath and Material(s) (MCP) for the Evacuation of the Residual Power in the Event of an Accident
US10020078B2 (en) Composite fuel rod cladding
Senor et al. A new innovative spherical cermet nuclear fuel element to achieve an ultra-long core life for use in grid-appropriate LWRs
EP2567383B1 (fr) Barre de commande pour réacteur nucléaire à eau légère
US20150063521A1 (en) Designed porosity materials in nuclear reactor components
Sato et al. Behavior of fuel and structural materials in severely damaged reactors
Onder Nuclear fuel
Shilyaev et al. Hafnium in nuclear power industry: the evolution of increasing of the economic indicators and the operation safety of pressurized water nuclear reactors
Tillack et al. Technology readiness of helium as a fusion power core coolant

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: 16876150

Country of ref document: EP

Kind code of ref document: A1

NENP Non-entry into the national phase

Ref country code: DE

32PN Ep: public notification in the ep bulletin as address of the adressee cannot be established

Free format text: NOTING OF LOSS OF RIGHTS PURSUANT TO RULE 112(1) EPC (EPO FORM 1205A DATED 28/09/2018)

122 Ep: pct application non-entry in european phase

Ref document number: 16876150

Country of ref document: EP

Kind code of ref document: A1