WO1994000848A1 - Faisceau de crayons combustibles de reacteur nucleaire a tete verrouillable - Google Patents

Faisceau de crayons combustibles de reacteur nucleaire a tete verrouillable Download PDF

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Publication number
WO1994000848A1
WO1994000848A1 PCT/DE1993/000519 DE9300519W WO9400848A1 WO 1994000848 A1 WO1994000848 A1 WO 1994000848A1 DE 9300519 W DE9300519 W DE 9300519W WO 9400848 A1 WO9400848 A1 WO 9400848A1
Authority
WO
WIPO (PCT)
Prior art keywords
fuel
fuel assembly
fuel element
support plate
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/DE1993/000519
Other languages
German (de)
English (en)
Inventor
Peter Rau
Walter Sauermann
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.)
Siemens AG
Siemens Corp
Original Assignee
Siemens AG
Siemens Corp
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 Siemens AG, Siemens Corp filed Critical Siemens AG
Priority to RU94046303/25A priority Critical patent/RU2111557C1/ru
Priority to SK1574-94A priority patent/SK157494A3/sk
Publication of WO1994000848A1 publication Critical patent/WO1994000848A1/fr
Priority to BG99275A priority patent/BG61413B1/bg
Priority to FI946132A priority patent/FI946132A0/fi
Anticipated expiration legal-status Critical
Ceased legal-status Critical Current

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
    • 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
    • G21C3/334—Assembling, maintenance or repair of the bundles
    • 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 invention relates to a nuclear reactor fuel element
  • a lower fuel rod holding body which rests loosely within the elongated fuel element box on the fuel element end body, stands on the long fuel rods containing elongated fuel rods with one end and on which a rod projecting above the fuel rods in the fuel element box with its upper end is attached to its lower end,
  • a fuel assembly head which is inserted into the upper end of the fuel assembly box and which can be locked against rotation in the fuel assembly box by rotating about the longitudinal axis of the fuel assembly box.
  • the rod projecting over the fuel rods with its upper end is an elongated tube which is screwed onto the lower fuel rod holding body and which extends through the support plate at the upper end of the fuel assembly box.
  • Each fuel rod engages loosely in the support plate with its upper end, and a compression spring is arranged on each fuel rod at the upper end, which is supported at one end on the inside of the support plate and at the other end on a step on the outer surface of the fuel rod in question.
  • the the tube reaching through the support plate can be an instrumentation tube for receiving thermocouples and / or neutron flux measuring lances.
  • an elongated rod can also be guided through this tube and screwed to the lower fuel rod holder body by rotating it about its longitudinal axis.
  • This rod represents a lifting device with which the fuel rod holder body lying loosely on the end element of the fuel element, together with the tube, the fuel rods, lattice-shaped spacers through which the tube and fuel rods are guided, and the support plate can be pulled out of the fuel element box.
  • Such shifting to a sufficient extent may, however, be impossible or lead to damage to the fuel rods if the length of at least individual fuel rods has increased too much after a certain service life of the nuclear reactor fuel element in a nuclear reactor and therefore the coil springs on the rod ends during insertion of the support plate in the fuel assembly box before unlatching the tongues from the pockets on the fuel assembly head on block.
  • Such a blocking of individual coil springs can be avoided by sufficient clearance for these coil springs. This would mean, however, that for a given rod length of the fuel rods, the length of the nuclear reactor fuel must be correspondingly large.
  • the reactor pressure vessel with its internals in which the nuclear reactor fuel element is used must also be designed to be correspondingly high. This means relatively high costs.
  • the object of the invention is to further develop the proposed nuclear reactor fuel element and to avoid damaging the fuel rods when the fuel element head is rotated out of its latching position even if the length of the nuclear reactor fuel element is relatively short.
  • a nuclear reactor fuel element of the type mentioned at the outset is characterized in accordance with the invention in that the support plate rests on the upper end of the rod projecting above the fuel rods and in that a spring leg is arranged between the fuel element head and the support plate, which is located both on the fuel element head and on supports the support plate.
  • the support plate resting on the rod shields the fuel rods from their locked position when the fuel assembly head is turned. At the same time, however, the distance between the support plate and the fuel rods can only be chosen to be large enough to provide space for the extension of the fuel rods during the service life of the nuclear reactor fuel element in a nuclear reactor.
  • Figure 1 is divided into sections 1A and 1B and shows a nuclear reactor fuel element according to the invention, which is cut longitudinally.
  • FIG. 2 shows a cross section corresponding to the dash-dotted line II-II in FIG. 1.
  • FIG. 3 shows a partial longitudinal section along the dash-dotted line III-III in FIG. 2.
  • the nuclear reactor fuel element according to FIGS. 1 to 3 has a fuel element end body 2, which is a fuel element foot.
  • This fuel assembly end body 2 is a hollow body made of stainless steel, which has an outer contour in the form of a regular hexagon at its upper end.
  • the fuel assembly end body 2 engages in an elongated fuel assembly box 3, which consists of a zirconium alloy.
  • the inner cross section of the fuel assembly 3 has a contour which is also a regular hexagon, so that this fuel assembly 3 lies at its lower end with the inner surface snugly against the outer surface of the fuel assembly 2 at its upper end.
  • the fuel assembly box 3 is rigidly attached to this fuel assembly end body 2 with radially directed screws 4.
  • the lower fuel rod holder body 5 is composed of stainless steel sleeves arranged side by side in a net-like manner.
  • the longitudinal axes of these sleeves are parallel to the longitudinal axis 3a of the fuel assembly box 3. Furthermore, the outer sides of these sleeves are firmly connected to one another by webs made of stainless steel.
  • fuel rods 8 are arranged, each of which loosely stands on a web of the lower fuel rod holder body 5 with a lower rod end.
  • a sleeve 6 forms a hole in the lower fuel rod holder body 5 designed as a leadthrough It also has an internal thread.
  • An elongated tube 9 made of a zirconium alloy is screwed into each of seven such sleeves 6 and has an external thread corresponding to the internal thread of the relevant sleeve 6 at the screwed-in tube end. At this screwed-in tube end, the tube 9 in question closes off with a cap nut 10, which is screwed into the relevant sleeve 6 on the outside of the lower fuel rod holder body 5 facing the fuel assembly body 2.
  • Such a cap nut 10 engages in each case in the cavity of the Brennele ⁇ mentend stresses 2. It has a central passage 11 in the longitudinal direction of Brennel 'ementkastens 3 for a liquid Coolant in a nuclear reactor. It also has an internal thread. The other tube end of the tubes 9 of the same length is located above the inside of the lower fuel rod holder body 5.
  • Both the fuel rods 8 and the tubes 9 projecting beyond the fuel rods 8 are each guided through a mesh of grid-shaped spacers.
  • These grid-shaped spacers have an outer contour in the form of a regular hexagon and are the contour of the inner cross section of the
  • Adjusted fuel assembly 3 In the meshes of these spacers, which are arranged at right angles to the longitudinal axis 3a of the fuel assembly 3 at a distance from one another in the longitudinal direction of this fuel assembly 3, the fuel rods 8 are held in a force-fitting manner by means of contact springs and rigid contact knobs. At least one tube 9 is held in each spacer by torsion-proof bodies. Furthermore, the spacers themselves are fixed on the outside by means of molded bodies to at least one tube 9 in the longitudinal direction of the fuel assembly box 3. These spacers are not shown in Figure 1.
  • a support plate 13 made of stainless steel within this fuel assembly 3, the outer contour of which in the form of a regular hexagon is adapted to the contour of the inner cross section of the fuel assembly 3 and which rests loosely on the fuel assembly 2 lower fuel rod holder body 5 is composed of sleeves with an axis and webs parallel to the longitudinal direction of the fuel assembly box 3.
  • This support plate 13 is loosely guided in the fuel assembly 3 and is arranged at right angles to the longitudinal axis 3a of the fuel assembly 3. It lies loosely on the open pipe ends of the pipes 9, which are above the
  • the support plate 13 On its inside facing the inside of the lower fuel rod holder body 5, the support plate 13 has centering bodies 14, which are screwed into a sleeve of the support plate 13 and engage loosely but largely without play in the open upper end of one of the tubes 9.
  • the tubes 9 can also loosely engage in a centering recess (not shown) on the inside of the support plate 13.
  • a fuel element head 17 is inserted into the upper end of the fuel element box 3.
  • This fuel assembly head 17 is a hollow body which has six spring struts 20 on its side facing the support plate 13. As shown in FIG. 3 in particular, such a strut has a pin 21 which is parallel to the longitudinal axis 3a of the fuel assembly 3 and is arranged at a distance from this longitudinal axis 3a and which has an elongated hole 22 in the fuel assembly head 17 through which a transverse pin is held in the fuel assembly head 17 23 takes hold.
  • the pin 21 With its end located in the fuel assembly head 17, the pin 21 engages in a helical spring 24 which is mounted with a longitudinal axis parallel to the longitudinal axis of the pin within a bore which is located in the fuel assembly head 17 and is parallel to the longitudinal axis 3 a of the fuel assembly box 3.
  • This coil spring 24 is supported at one end on the bottom of this bore and at the other end on a shoulder on the outside of the pin 21.
  • the pin 21 of each of the spring struts 20 engages with its end located outside the fuel assembly head 17 into a latching recess 25 in the outside of the support plate 13 facing the fuel assembly head 17.
  • the pins 21 of the struts 20 are moved in the longitudinal direction of the fuel assembly box 3 with a tool guided through the cavity of the fuel assembly head 17, which engages behind a shoulder 21a in the lateral surface of the pins 21 of the struts 20 moved towards the fuel assembly head 17 into the fuel assembly head 17 until these pins 21 disengage from the latching recesses 25 in the support plate 13.
  • the fuel assembly head 17 can then be rotated from the locking position shown in FIGS. 1 and 2 about the longitudinal axis 3a of the fuel assembly box 3 into another end position in which the peripheral ribs 18 are unscrewed at the slots 19 and in which the fuel assembly head 17 is removed from the fuel assembly box 3 can be pulled out.
  • an elongated rod with an end having an external thread can be guided through a centrally arranged tube 9 to the union nut 10 and can be rotated about the longitudinal axis of the rod with the internal thread of the union nut 10 be screwed. Then, with the aid of the rod representing a hoist, the lower fuel rod holder body 5 loosely resting on the fuel element end body 2 together with all the tubes 9, the fuel rods 8, the grid-shaped spacers (not shown) and the support plate 13 can be pulled out of the fuel element box 3.

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Resistance Heating (AREA)

Abstract

Des crayons combustibles allongés (8) situés à l'intérieur d'une caisse allongée (3) d'éléments combustibles reposent par une extrémité sur un corps inférieur de support (5), sur lequel est également assujettie par son extrémité inférieure une barre (9) qui fait saillie au-dessus des crayons combustibles (8). Une plaque de support (13) guidée mobile dans la caisse (3) d'éléments combustibles repose sur l'extrémité supérieure de la barre (9) afin de prévenir l'endommagement des crayons de combustibles (8). Une tête (17) d'élément combustible est insérée sur l'extrémité supérieure de la caisse (3) d'éléments combustibles et peut être mise en rotation autour de l'axe longitudinal (3a) de ladite caisse (3) jusqu'à s'encliqueter de manière à résister aux torsions. Un montant à ressort (20) situé entre la tête (17) d'élément combustible et la plaque de support (13) s'appuie aussi bien sur ladite tête (17) que sur la plaque de support (13). Pour le démontage, il n'est donc pas nécessaire de déplacer la plaque de support en direction du corps inférieur de support des crayons combustibles, ce qui risquerait d'endommager ces derniers, ou bien exigerait un écartement correspondant plus élevé.
PCT/DE1993/000519 1992-06-29 1993-06-16 Faisceau de crayons combustibles de reacteur nucleaire a tete verrouillable Ceased WO1994000848A1 (fr)

Priority Applications (4)

Application Number Priority Date Filing Date Title
RU94046303/25A RU2111557C1 (ru) 1992-06-29 1993-06-16 Тепловыделяющий элемент ядерного реактора
SK1574-94A SK157494A3 (en) 1992-06-29 1993-06-16 Nuclear reactor fuel element
BG99275A BG61413B1 (en) 1992-06-29 1994-12-19 Fuel element of a nuclear reactor
FI946132A FI946132A0 (fi) 1992-06-29 1994-12-28 Ydinreaktorin polttoaine-elementti

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
DE4221301A DE4221301A1 (de) 1992-06-29 1992-06-29 Kernreaktorbrennelement
DEP4221301.0 1992-06-29

Publications (1)

Publication Number Publication Date
WO1994000848A1 true WO1994000848A1 (fr) 1994-01-06

Family

ID=6462073

Family Applications (1)

Application Number Title Priority Date Filing Date
PCT/DE1993/000519 Ceased WO1994000848A1 (fr) 1992-06-29 1993-06-16 Faisceau de crayons combustibles de reacteur nucleaire a tete verrouillable

Country Status (8)

Country Link
BG (1) BG61413B1 (fr)
CZ (1) CZ281841B6 (fr)
DE (1) DE4221301A1 (fr)
FI (1) FI946132A0 (fr)
HU (1) HU214072B (fr)
RU (1) RU2111557C1 (fr)
SK (1) SK157494A3 (fr)
WO (1) WO1994000848A1 (fr)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO1996003752A1 (fr) * 1994-07-22 1996-02-08 Siemens Aktiengesellschaft Faisceau de crayons combustibles assembles a l'aide de tenons

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
RU2190263C2 (ru) * 1999-10-22 2002-09-27 Открытое акционерное общество "Новосибирский завод химконцентратов" Тепловыделяющая сборка ядерного реактора

Citations (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
SU708830A1 (ru) * 1978-06-15 1983-04-07 Предприятие П/Я Г-4285 Топливна сборка дерного реактора
SU784570A1 (ru) * 1979-03-28 1983-04-07 Предприятие П/Я Г-4285 Верхн концева деталь топливной сборки
SU665556A1 (ru) * 1977-12-19 1985-05-15 Предприятие П/Я М-5881 Тепловыдел юща сборка
JPH02195295A (ja) * 1989-01-25 1990-08-01 Nuclear Fuel Ind Ltd 原子燃料集合体
WO1992010839A1 (fr) * 1990-12-05 1992-06-25 Siemens Aktiengesellschaft Element combustible ou element de commande avec dispositif de verrouillage liberable monte entre le caisson et l'extremite superieure ou inferieure de l'element
DE4041349A1 (de) * 1990-12-21 1992-06-25 Siemens Ag Kernreaktorbrennelement

Patent Citations (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
SU665556A1 (ru) * 1977-12-19 1985-05-15 Предприятие П/Я М-5881 Тепловыдел юща сборка
SU708830A1 (ru) * 1978-06-15 1983-04-07 Предприятие П/Я Г-4285 Топливна сборка дерного реактора
SU784570A1 (ru) * 1979-03-28 1983-04-07 Предприятие П/Я Г-4285 Верхн концева деталь топливной сборки
JPH02195295A (ja) * 1989-01-25 1990-08-01 Nuclear Fuel Ind Ltd 原子燃料集合体
WO1992010839A1 (fr) * 1990-12-05 1992-06-25 Siemens Aktiengesellschaft Element combustible ou element de commande avec dispositif de verrouillage liberable monte entre le caisson et l'extremite superieure ou inferieure de l'element
DE4041349A1 (de) * 1990-12-21 1992-06-25 Siemens Ag Kernreaktorbrennelement

Non-Patent Citations (4)

* Cited by examiner, † Cited by third party
Title
PATENT ABSTRACTS OF JAPAN vol. 14, no. 482 (P-1119)19. Oktober 1990 & JP,A,02 195 295 ( NUCLEAR FUEL IND ) 1. August 1990 *
SOVIET INVENTIONS ILLUSTRATED Section Ch, Week 8406, 21. März 1984 Derwent Publications Ltd., London, GB; Class K, AN 84-035092 & SU,A,784 570 (KIRILYUK) 7. April 1983 *
SOVIET INVENTIONS ILLUSTRATED Section Ch, Week 8409, 1. April 1984 Derwent Publications Ltd., London, GB; Class K, AN 84-054116 & SU,A,708 830 (VASILCHENKO) 7. April 1983 *
SOVIET INVENTIONS ILLUSTRATED Section Ch, Week 8535, 10. Oktober 1985 Derwent Publications Ltd., London, GB; Class K, AN 85-215277 & SU,A,665 556 (OVCHINNIKOV) 15. Mai 1985 *

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO1996003752A1 (fr) * 1994-07-22 1996-02-08 Siemens Aktiengesellschaft Faisceau de crayons combustibles assembles a l'aide de tenons
US5787143A (en) * 1994-07-22 1998-07-28 Siemens Aktiengesellchaft Nuclear reactor fuel assembly

Also Published As

Publication number Publication date
CZ281841B6 (cs) 1997-02-12
FI946132A7 (fi) 1994-12-28
HUT69811A (en) 1995-09-28
RU94046303A (ru) 1996-10-20
DE4221301A1 (de) 1994-01-05
CZ316094A3 (en) 1995-04-12
HU214072B (en) 1997-12-29
BG99275A (bg) 1995-11-30
SK157494A3 (en) 1995-06-07
RU2111557C1 (ru) 1998-05-20
BG61413B1 (en) 1997-07-31
FI946132A0 (fi) 1994-12-28

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