WO1995007537A1 - Reduction, dans le c×ur d'un reacteur, du nombre de barres de combustible protegees contre l'interaction gaine-pellet - Google Patents

Reduction, dans le c×ur d'un reacteur, du nombre de barres de combustible protegees contre l'interaction gaine-pellet Download PDF

Info

Publication number
WO1995007537A1
WO1995007537A1 PCT/SE1994/000836 SE9400836W WO9507537A1 WO 1995007537 A1 WO1995007537 A1 WO 1995007537A1 SE 9400836 W SE9400836 W SE 9400836W WO 9507537 A1 WO9507537 A1 WO 9507537A1
Authority
WO
WIPO (PCT)
Prior art keywords
fuel
rods
group
core
cladding
Prior art date
Application number
PCT/SE1994/000836
Other languages
English (en)
Inventor
Olov Nylund
Original Assignee
Abb Atom 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 Abb Atom Ab filed Critical Abb Atom Ab
Priority to DE9421670U priority Critical patent/DE9421670U1/de
Priority to EP94926455A priority patent/EP0722610A1/fr
Publication of WO1995007537A1 publication Critical patent/WO1995007537A1/fr
Priority to FI961094A priority patent/FI961094A0/fi

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
    • G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements
    • G21C3/326—Bundles of parallel pin-, rod-, or tube-shaped fuel elements comprising fuel elements of different composition; comprising, in addition to the fuel elements, other pin-, rod-, or tube-shaped elements, e.g. control rods, grid support rods, fertile rods, poison rods or dummy rods
    • G21C3/328—Relative disposition of the elements in the bundle lattice
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/02—Fuel elements
    • G21C3/04—Constructional details
    • G21C3/16—Details of the construction within the casing
    • G21C3/20—Details of the construction within the casing with coating on fuel or on inside of casing; with non-active interlayer between casing and active material with multiple casings or multiple active layers
    • 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

  • the present invention relates to a fuel assembly comprising a plurality of fuel rods in which each fuel rods comprises a cladding tube which encloses a nuclear fuel.
  • the fuel assembly is arranged adjacent to one or more control rod positions and contains a first group of fuel rods provided with PCI protection and a second group of fuel rods without PCI protection.
  • the first group of fuel rods lies nearer the central part of a control rod position than does the second group.
  • the invention also relates to a core comprising a plurality of fuel assemblies and a plurality of control rods.
  • the con ⁇ trol rods can both be inserted into and withdrawn from the core.
  • a first group of control rods at least certain con- trol rods are partially inserted into the core during normal operation of the reactor.
  • a second group of control rods all the control rods are withdrawn from the core during normal operation.
  • a core in a nuclear reactor comprises a plurality of fuel assemblies. These are arranged vertically in the core in a certain spaced relationship to each other.
  • a fuel assembly comprises a plurality of vertical fuel rods which contains a stack of circular-cylindrical pellets of a nuclear fuel arranged in a cladding tube.
  • the core is immersed into water which serves both as a coolant and as a neutron moderator.
  • the reactor core also comprises a number or control rods which control the reactivity of the core, and hence the output power thereof, by being inserted into and withdrawn from the core.
  • control rod positions - are different for different reactors.
  • a control rod position is meant the entire space occupied by a control rod fully inserted into the core. Some of the control rods are withdrawn from the core during operation. The other control rods are inser ⁇ ted to different levels in the core. These levels vary during the operating cycle of the reactor.
  • PCI damage pellet-clad interaction
  • cladding tubes normally thin-walled tubes of zirconium-based alloys are used, which are known under the trade name zircaloy. These alloys irradiation-harden under neutron irradiation. The irradiation hardening leads to an embrittlement of the material.
  • the power rapidly increases, mechanical stresses arise due to differences in extension between the fuel and the cladding. These stresses may lead to cracks in the embrittled cladding tube. The mechanical stresses are reinforced by high friction between the fuel and the cladding.
  • the cladding tube internally with a protective layer of metal, a so-called liner, which has good resistance to hardening when subjected to neutron irradiation and which in itself is a relatively soft material. Because of the properties mentioned, the liner can be deformed plastically and thereby protect the cladding tube against stresses, caused by the nuclear fuel, which arise during operation in case of rapid changes of power in combination with high temperatures at the centre of the rod.
  • the liner may, for example, be a pure zirconium or of some zirconium alloy.
  • liners generally have a low resistance to corrosion by water and water steam.
  • corrosion products are formed which accelerate the embrittlement of the cladding tube.
  • external damage to the cladding tube arises, for example abrasion damage, water and water steam may penetrate into the interior of the cladding tube and the liner starts corroding.
  • a fuel rod with a liner exhibits considerably more serious damage than a fuel rod without a liner.
  • An additional disadvantage of using cladding tubes with liners is that the mechanical strength is inferior compared with a cladding tube without a liner.
  • a liner is most often made of pure zirconium or some zirconium alloy and has a very low neutron absorption cross section. Therefore, no problem corresponding to that described in the Japanese application exists with PCI protection in the form of a liner.
  • the object of the invention is to reduce the risk of serious abrasion damage in a reactor core without increasing the risk of PCI damage.
  • a reduced risk of serious abrasion damage is achieved by reducing the number of fuel rods with liners in the core.
  • fuel rods with liners are arranged only in certain positions which are particularly exposed to PCI damage, whereas fuel rods without liners are arranged in the other positions.
  • the invention aims to provide a fuel assembly for a boiling water reactor in which the number of fuel rod positions in the fuel assembly is greater than 80, and a fuel assembly for a boiling water reactor in which the number of fuel rod positions in the fuel assembly is smaller than 65.
  • the invention also aims to provide a fuel assembly for a pressurized-water reactor.
  • the invention also aims to provide a core in a boiling water reactor and a core in a pressurized-water reactor, in which the number of fuel rods with liners is reduced without the risk of PCT damage increasing.
  • the invention is therefore particularly advantageous for fuel assemblies with a high rod density (more than 80 fuel rod positions) , since these involve
  • Figure 1 shows a horizontal section of part of a reactor core for a boiling reactor with vertical fuel assemblies according to the prior art .
  • Figure 2 shows a fuel rod in a vertical section.
  • Figures 3a - 3g shows in horizontal sections a number of embodiments of a fuel assembly according to the invention.
  • Figures 4a - 4f show in horizontal sections alternative embodiments of a fuel assembly according to the invention.
  • Figures 5a - 5c show horizontal sections of a number of embodiments of a fuel assembly for a pressurized-water reactor according to the invention.
  • Figure 6 shows a horizontal section through a core in a boiling water reactor according to the invention.
  • Figure 7 shows a horizontal section through a core in a pressurized-water reactor according to the invention.
  • Figure 1 shows horizontal section of part of a reactor core for a boiling reactor with fuel assemblies according to the prior art.
  • the fuel assemblies have a substantially square cross section and are arranged vertically in the core in a certain spaced relationship to each other. This leads to the formation of a check pattern of vertically standing gaps between the fuel assemblies.
  • the section includes nine fuel assemblies la-li. The total number of fuel assemblies in a whole cross section amounts to several hundred.
  • the fuel assembly is enclosed in a fuel channel 2 which is provided with a hollow support member 3 of cruciform cross section.
  • the support member has four hollow wings 4 which form a central channel 5 where moderator water circulates.
  • the fuel channel with support members is divided into four vertical channel-formed parts with at least substantially square cross section, each one comprising a sub-bundle 6.
  • Each sub-bundle 6 contains a number of fuel rods 7.
  • the rods are arranged in a lattice in which each rod 7 is included in two rows perpendicular to each other.
  • the rods are retained in their positions by means of so-called spacers (not shown) , placed between top tie plates and bottom tie plates (also not shown) on the fuel assembly.
  • the spaces 8 between the fuel rods within each sub-assembly 6 are traversed by water.
  • the gaps 9a and 9b between the fuel assemblies are also traversed by water.
  • the reactor core also comprises a number of control rods, lla-lld, placed in parallel with the fuel assemblies in the vertically extending gaps.
  • the control rods have a cruciform cross section with four blades, extending perpendicularly to each other from a central part 12, which form a right-angled cross.
  • the gaps 9b into which the control rods can be inserted are wider than the gaps 9a where there are no control rods.
  • a control rod position 10 for a control rod for a boiling water reactor is meant the entire cruciform space which is occupied by a control rod fully inserted into the core.
  • the fuel assemblies are arranged in a symmetrical lattice with each fuel assembly included in two rows of fuel assem ⁇ blies perpendicular to each other.
  • the control rods are arranged with each one of their blades between two fuel assemblies located in the same row, such that each control rod together with four fuel assemblies, arranged around their blades, form a unit, hereinafter referred to as a supercell, with at least substantially square cross section.
  • the control rod lie forms together with the fuel assemblies Id, le, lg and lh a supercell.
  • each fuel rod 7 accommodates a cladding tube 20 and a large number of circular-cylindrical pellets 21 stacked one above the other in the axial direction of the tube.
  • the lowermost pellet rests rigidly on a bottom plug 22 welded to the lower end of the rod, and the uppermost pellet is pressed downwards by a spiral spring 23 which is tightened against a top plug 24 welded to the upper end of the tube.
  • FIG 3a shows one embodiment of the invention.
  • the fuel assembly 1 is provided with an enlarged centre in that the cruciform channel is formed with internal corner reductions (prior art according to Swedish patent 454 822) .
  • the fuel assembly comprises a first group of fuel rods provided with PCI pro ⁇ tection 7a to prevent cladding damage caused by the inter ⁇ action of the nuclear fuel with the cladding tube, as well as a second group of fuel rods without such protection.
  • the first group includes all the fuel rods which adjoin the con ⁇ trol rod position 10 as well as the three rods which have the shortest distance to the cruciform centre without imme ⁇ diately adjoining the control rod position.
  • the PCI protection consists of a protective layer, a so-called liner, of a zirconium alloy arranged on the internal surface of the cladding tube.
  • a liner is described in Swedish patent application 9200584-2.
  • the fuel rods are placed in a substantially regular lattice.
  • a fuel rod position is meant a position in the lattice. All the fuel rod positions in the lattice need not be occu-pie by fuel rods.
  • a number of fuel rods are replaced by one or more water channels . The introduction of a water channel changes the number of fuel rods but not the number of fuel rod positions.
  • Fuel assem- blies with the same external dimensions may have different numbers of fuel rod positions.
  • the rod density of a fuel assembly is defined as the number of fuel rod positions per unit of surface. In an assembly with a high rod density, the fuel rods are generally thinner than the fuel rods in an assembly with a smaller rod density.
  • the number of fuel rod positions per assembly may, for a boiling reactor, vary from 7x7, that is, 49, in older types of assemblies to 11x11, that is, 121, in certain modern assemblies.
  • the invention is particularly suitable for assemblies in which the number of fuel rod positions is greater than or equal to 9x9, that is, 81.
  • Figures 3a-3g show a number of different embodiments of the invention in which the number of fuel rods in the first and second groups vary. Which rods are included in the two groups are clear from the figures. If the risk of cladding damage is judged to be high, an alternative with many rods with liners, 7a, is chosen, for example Figure 3c or Figure 3d. If the risk of cladding damage is judged to be low, an alternative with few rods with liners is chosen, for example Figure 3f or Figure 3g. Common to all the embodiments is that the first group of fuel rods lies nearer to the central part of the control rod position than does the second group.
  • Individual fuel rods in the second group may lie nearer to the central part of the control rod position than certain fuel rods in the first group.
  • a group is meant the group as an entirety.
  • the mean distance of a group to the central part of a control rod position is calculated as the sum of the distance between each fuel rod associated with the group and the central part of the nearest control rod position, divided by the number of fuel rods in the group.
  • FIGS 4a-4f show other fuel assemblies which are suitable for use according to the invention.
  • Each type of fuel assem ⁇ bly is provided in the figure with a first group of fuel rods provided with liners 7a, and with a second group of fuel rods without liners.
  • the number of fuel rods with liners in each assembly is only an example, and, in prin ⁇ ciple, all the embodiments described in Figures 3a-3g are . also applicable to these fuel assemblies.
  • Assemblies with a high rod density normally are provided with a smaller number of rods with liners, relatively seen, than assemblies with a lower rod density.
  • the embodiments in Figures 4c, 4d and 4f are not suitable for an 8x8 fuel .
  • Figure 4a shows a fuel assembly without an internal water channel.
  • the number of fuel rod positions is 64.
  • Figure 4b shows a fuel assembly provided with a central cruciform channel 5 through which water is passed in a vertical direction from below and upwards through the assembly.
  • the number of fuel rod positions is 64.
  • Figure 4c shows a fuel assembly provided with a central cruciform channel 5.
  • the number of fuel rod positions is 100.
  • Figure 4d shows a fuel assembly provided with an internally arranged vertical channel 30 through which water is passed in a vertical direction from below and upwards through the assembly.
  • the channel has a substantially square cross section.
  • the number of fuel rod positions is 81.
  • Figure 4e shows a fuel assembly provided with an internally arranged vertical channel 31 through which water is passed from below and upwards through the assembly.
  • the number of fuel rod positions is 64.
  • Figure 4f shows a fuel assembly which is provided with two centrally arranged vertical water rods 32 through which water is passed from below and upwards through the assembly.
  • the water rods have a diameter which is somewhat larger than the diameter of the fuel rods and is formed with a substan ⁇ tially circular cross section.
  • the number of fuel rod posi ⁇ tions is 81.
  • FIG. 5a shows a fuel assembly for a pressurized-water reactor according to the invention, which comprises control rod positions 40, an instrumentation tube 41, fuel rods with liners, 42a, and fuel rods without liners, 42b.
  • the control rod positions for a pressurized-water reactor are located inside the fuel assemblies, in contrast to a boiling reactor which has the control rod positions between the assemblies.
  • the control rods which are 24 in number have a substantially circular cross section and a diameter which is somewhat larger than the diameter of the fuel rods.
  • the fuel rods which imme ⁇ diately adjoin a control rod position form a first group of fuel rods which are provided with liners, 42a. For each control rod position there are four immediately adjoining fuel rods.
  • the other fuel rods have no liners, 42b, and are included in a second group of fuel rods.
  • Figure 5b shows another embodiment of the invention in which all fuel rods adjoining a control rod position form a first group of fuel rods which are provided with liners, 42a. For each control rod position there are eight immediately adjoining fuel rods. The other fuel rods have no liners, 42b, and are included in a second group of fuel rods. In this embodiment, the number of fuel rods in the first group is greater than the number of fuel rods in the second group.
  • Figure 5c shows another type of fuel assembly for a pressurized-water reactor.
  • the control rod positions 50 which are five in number have a substantially circular cross section and a diameter which is considerably larger than the diameter of the fuel rods. All the fuel rods adjoining a control rod position form a first group of fuel rods which are provided with liners 42a. For each control rod position there are twelve immediately adjoining fuel rods. The other fuel rods have no liners 42b and are included in a second group of fuel rods.
  • the top plug or the bottom plug is suitably provided with some form of marking.
  • regulating rods In a boiling water reactor there is a small number of specially selected control rods, so-called regulating rods, which are used during operation to compensate for the burnup of the fuel. The other control rods are then fully withdrawn from the core. At the beginning of an operating cycle, that is, the time between two refuellings, the regulating rods are at least partially inserted into the core. To compensate for the burnup of the fuel, the regulating rods are with ⁇ drawn successively during the operating cycle. The control rods which do not belong to the regulating rods are used to start and stop the reactor. A supercell which contains a regulating rod is referred to hereinafter as a control cell.
  • the duration of an operating cycle is usully one year, but it varies and may in certain reactors be up to two years.
  • the number of operating cycles during which the fuel, on average, is located in the core before refuelling also varies between different reactors.
  • an operating cycle is one year and the average time for a fuel assembly in the core is 5 cycles, about one-fifth of the fuel assemblies need to be replaced by new ones each year.
  • the fuel assemblies in the control cells are charged with fuel which has a relatively high burnup.
  • these assemblies have been placed during one or more operating cycles in some of the other super ⁇ cells. Normally, the fuel assemblies in the control cells usually sit there during one operating cycle only.
  • Figure 6 shows a horizontal section through a core in a boiling water reactor.
  • the core comprises a large number of supercells 60a, 60b, arranged in a symmetrical lattice with each supercell included in two rows of supercells perpendi- cular to each other.
  • Nine of the supercells comprise control elements, so-called control cells, 60b.
  • the other super ⁇ cells, 60a comprise control rods which are fully withdrawn during normal operation.
  • Each supercell comprises four fuel assemblies 61a, 61b.
  • the fuel assemblies in the control cells run a higher risk of PCI damage than the other supercells.
  • the risk of PCI damage in the other super- cells is so small that the fuel rods may be completely without liners.
  • the fuel assembly 61a is completely without a liner on the rods.
  • the risk of PCI damage is still so high that a liner is necessary.
  • the fuel assemblies in the control rods, 61b may, for example, be some of the assemblies in Figures 3a-3g or 4a-4f. It is also possible that all the fuel rods in the fuel assembly 61b have liners.
  • the risk of serious abrasion damage is reduced, while at the same time the risk of PCI damage is kept low, if at least certain fuel rods in those fuel assemblies which are included in the control cells are provided with liners, while at the same time as many as possible of the other fuel assemblies have no liners.
  • Fuel assemblies which include fuel rods with liners are herein ⁇ after referred to as liner assemblies.
  • the fuel assemblies usually are only allowed to sit during one operating cycle in the control cells, and that these, in addition, shall have a certain burnup, makes it necessary for the core upon each refuelling to be supplied with, on average, at least as many liner assemblies as the total number of fuel assemblies in all the control cells, that is, 4 x N, where N is the number of control cells in the core.
  • N is the number of control cells in the core.
  • this means that the core must be supplied with at least 4 x 9 36 liner assemblies upon each refuelling.
  • the number of control cells varies usually between five and twelve depending on the operating conditions, but smaller and greater values may occur.
  • the total number of liner assemblies in the core is then at least C x 4 x N, where C is the average number of operating cycles during which a fuel assembly sits in the core.
  • C is the average number of operating cycles during which a fuel assembly sits in the core.
  • the number of liner assemblies must not be too great since this increases the risk of serious abrasion damage.
  • the number of extra liner assemblies in the core may be 20% at most.
  • the total number of liner assemblies in the core may be l.2 x C x 4 x at most, and these are substantially evenly distributed with respect to burnup time.
  • the core in Figure 6 contains 444 fuel assemblies and nine control cells.
  • the average number of operating cycles during which a fuel assembly sits in the core is 5.
  • Figure 7 shows a horizontal section through a core in a pressurized-water reactor comprising a plurality of fuel assemblies, 70a, 70b, 70c.
  • Certain of the fuel assemblies 70, 70c comprise a number of control rods.
  • a first group of fuel assemblies 70b comprises control rods which during operation are used for power control. This first group is normally divided into several sub-groups for, for example, power level control and power shaping. The division of the control rods into sub-groups varies between different reactors.
  • a second group of fuel assemblies 70c comprises control rod which are all, during normal operation, with ⁇ drawn from the core and only used for starting and stopping the reactor. The other fuel assemblies 70a do not comprise any control rods.
  • all the fuel assemblies 70b in the first group comprise fuel rods in which the inside of the cladding tube is provided with a liner, and the total number of fuel assemblies in the whole core which comprises fuel rods with liners shall be smaller than 1.2 x C x N, where N is the average number of operating cycles during which a fuel assembly sits in the core, and N is the number of fuel assemblies in the first group.
  • the fuel assemblies in the first group only have liners on those fuel rods which are placed in particularly exposed positions in the vicinity of a control rod position. Suitable fuel assemblies 70b to use in the first group are shown in Figures 5a, 5b and 5c.
  • Normal operation is meant operation with the power variations which are normally required by the reactor to adapt to the requirement of the network. Normal operation comprises daily load cycling, weekend load cycling, and frequency control.

Landscapes

  • 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)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

L'invention concerne l'assemblage combustible d'un réacteur à eau bouillante pouvant recevoir plus de 80 barres de combustible, ou moins de 65 barres de combustible, et l'assemblage combustible d'un réacteur à eau pressurisée. Un assemblage combustible se compose de plusieurs barres de combustibles qui sont toutes constituées de combustible nucléaire entrouré d'une gaine. L'assemblage combustible est situé à proximité d'un ou plusieurs emplacements (10) de barres de contrôle. Pour protéger la barre de combustible contre les risques d'interaction gaine-pellet, l'intérieur de la gaine est muni d'une couche métallique de protection. Seules les barres de combustible (7a) des emplacements les plus spécifiquement exposées, c'est-à-dire à proximité de l'emplacement de la barre de contrôle, sont munies d'une gaine de protection. Les autres barres de combustible (7b) ne disposent pas de gaine de protection. L'invention concerne également un c÷ur de réacteur à eau bouillante et un c÷ur de réacteur à eau pressurisée dans lesquels tous les ensembles combustibles contiennent une barre de combustible à gaine de protection, qu'ils contiennent la barre de contrôle ou qu'ils soient placés à proximité d'elle, cette barre de contrôle étant parfois introduite dans le c÷ur du réacteur pendant le fonctionnement normal. Le nombre total d'ensembles combustibles dans l'ensemble du c÷ur est inférieur à 1,2 x C x M, C étant le nombre moyen de cycles de fonctionnement pendant lesquels l'ensemble combustible peut être placé dans le c÷ur, et M étant le nombre d'ensembles combustibles contenant la barre de contrôle ou placés à proximité d'elle, cette barre de contrôle étant parfois introduite dans le c÷ur du réacteur pendant le fonctionnement normal.
PCT/SE1994/000836 1993-09-09 1994-09-08 Reduction, dans le c×ur d'un reacteur, du nombre de barres de combustible protegees contre l'interaction gaine-pellet WO1995007537A1 (fr)

Priority Applications (3)

Application Number Priority Date Filing Date Title
DE9421670U DE9421670U1 (de) 1993-09-09 1994-09-08 Reaktorkern mit einer verminderten Anzahl von PCI-geschützten Brennstäben
EP94926455A EP0722610A1 (fr) 1993-09-09 1994-09-08 Reduction, dans le c ur d'un reacteur, du nombre de barres de combustible protegees contre l'interaction gaine-pellet
FI961094A FI961094A0 (fi) 1993-09-09 1996-03-08 PCI-suojattujen polttoainesauvojen lukumäärän alentaminen reaktorin sydämessä

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
SE9302933A SE9302933L (sv) 1993-09-09 1993-09-09 Förfarande för att minska antalet kapslingsskyddade bränslestavar i en kärnreaktors bränslepatron, och en bränslepatron enligt förfarandet
SE9302933-8 1993-09-09

Publications (1)

Publication Number Publication Date
WO1995007537A1 true WO1995007537A1 (fr) 1995-03-16

Family

ID=20391044

Family Applications (1)

Application Number Title Priority Date Filing Date
PCT/SE1994/000836 WO1995007537A1 (fr) 1993-09-09 1994-09-08 Reduction, dans le c×ur d'un reacteur, du nombre de barres de combustible protegees contre l'interaction gaine-pellet

Country Status (6)

Country Link
EP (1) EP0722610A1 (fr)
JP (1) JP3039483U (fr)
DE (1) DE9421670U1 (fr)
FI (1) FI961094A0 (fr)
SE (1) SE9302933L (fr)
WO (1) WO1995007537A1 (fr)

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE29813359U1 (de) * 1998-07-27 1999-09-02 Siemens Ag Brennelement für einen Siedewasserreaktor

Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0243917A1 (fr) * 1986-04-29 1987-11-04 Ab Asea-Atom Assemblage de combustible nucléaire
EP0264820A2 (fr) * 1986-10-17 1988-04-27 Westinghouse Electric Corporation Elément de combustible nucléaire résistant à l'interaction gaine-comprimé

Patent Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0243917A1 (fr) * 1986-04-29 1987-11-04 Ab Asea-Atom Assemblage de combustible nucléaire
EP0264820A2 (fr) * 1986-10-17 1988-04-27 Westinghouse Electric Corporation Elément de combustible nucléaire résistant à l'interaction gaine-comprimé

Non-Patent Citations (1)

* Cited by examiner, † Cited by third party
Title
PATENT ABSTRACTS OF JAPAN, Vol. 14, No. 98, P-1011; & JP,A,1 304 389 (TOSHIBA CORP), 7 December 1989 (07.12.89). *

Also Published As

Publication number Publication date
DE9421670U1 (de) 1996-11-07
SE9302933L (sv) 1995-03-10
FI961094A (fi) 1996-03-08
FI961094A0 (fi) 1996-03-08
JP3039483U (ja) 1997-07-22
EP0722610A1 (fr) 1996-07-24
SE9302933D0 (sv) 1993-09-09

Similar Documents

Publication Publication Date Title
US6347130B1 (en) Fuel assembly with short fuel units
US5872826A (en) Fuel assembly channel box having burnable poison
US6327324B2 (en) Nuclear fuel assembly
JPH07101237B2 (ja) 燃料集合体及び原子炉
US20080181350A1 (en) MOX fuel assembly for pressurized nuclear reactors
EP1149387B1 (fr) Barre de controle
EP0871960B1 (fr) Ensemble combustible pour reacteur a eau bouillante
US6885722B2 (en) Fuel assembly
EP0722610A1 (fr) Reduction, dans le c ur d'un reacteur, du nombre de barres de combustible protegees contre l'interaction gaine-pellet
US5610959A (en) Hafnium doped replacement rod for nuclear fuel reconstitution
US5349619A (en) Fuel assembly for light water reactor and light water reactor core
US5422922A (en) Fuel assembly and reactor core
US5319685A (en) Method for operation of a boiling water nuclear reactor
JP3339768B2 (ja) 軽水型原子炉炉心
JP4351798B2 (ja) 燃料集合体および原子炉
EP1012851B1 (fr) Assemblage combustible nucleaire
RU2236712C2 (ru) Регулирующая тепловыделяющая сборка водо-водяного энергетического реактора
JP4409191B2 (ja) 沸騰水型原子炉用燃料集合体
JPS63234192A (ja) 原子炉用燃料集合体
JP2953789B2 (ja) 核燃料集合体
JP2003262692A (ja) 沸騰水型原子炉用燃料集合体及び該燃料集合体内の燃料棒配置の決定法
JPH01276095A (ja) 燃料集合体
JPH04238292A (ja) 沸騰水型原子炉
JP2004333432A (ja) 原子炉の燃料装荷方法
JP2003161793A (ja) 沸騰水型原子炉用燃料集合体

Legal Events

Date Code Title Description
AK Designated states

Kind code of ref document: A1

Designated state(s): FI JP KP KR US

AL Designated countries for regional patents

Kind code of ref document: A1

Designated state(s): AT BE CH DE DK ES FR GB GR IE IT LU MC NL PT SE

DFPE Request for preliminary examination filed prior to expiration of 19th month from priority date (pct application filed before 20040101)
121 Ep: the epo has been informed by wipo that ep was designated in this application
WWE Wipo information: entry into national phase

Ref document number: 1994926455

Country of ref document: EP

WWE Wipo information: entry into national phase

Ref document number: 961094

Country of ref document: FI

WWP Wipo information: published in national office

Ref document number: 1994926455

Country of ref document: EP

WWW Wipo information: withdrawn in national office

Ref document number: 1994926455

Country of ref document: EP