EP1512155A1 - Procede et dispositif pour eliminer une gaine d'elements combustibles dans une centrale nucleaire a reacteur a eau bouillante - Google Patents

Procede et dispositif pour eliminer une gaine d'elements combustibles dans une centrale nucleaire a reacteur a eau bouillante

Info

Publication number
EP1512155A1
EP1512155A1 EP03759894A EP03759894A EP1512155A1 EP 1512155 A1 EP1512155 A1 EP 1512155A1 EP 03759894 A EP03759894 A EP 03759894A EP 03759894 A EP03759894 A EP 03759894A EP 1512155 A1 EP1512155 A1 EP 1512155A1
Authority
EP
European Patent Office
Prior art keywords
fuel assembly
support structure
stabilized
boiling water
water reactor
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Granted
Application number
EP03759894A
Other languages
German (de)
English (en)
Other versions
EP1512155B1 (fr
Inventor
Wolfgang Hummel
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.)
Areva GmbH
Original Assignee
Framatome ANP GmbH
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 Framatome ANP GmbH filed Critical Framatome ANP GmbH
Publication of EP1512155A1 publication Critical patent/EP1512155A1/fr
Application granted granted Critical
Publication of EP1512155B1 publication Critical patent/EP1512155B1/fr
Anticipated expiration legal-status Critical
Expired - Lifetime legal-status Critical Current

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F5/00—Transportable or portable shielded containers
    • G21F5/005—Containers for solid radioactive wastes, e.g. for ultimate disposal

Definitions

  • the invention relates to a method for disposing of a fuel assembly box.
  • the invention relates to a method and a device for the disposal of radioactive contaminated parts of a boiling water reactor system.
  • the fuel assembly box 4 is open at its end faces and is only provided on one end face at opposite corners with support struts 8a which are used to fasten the fuel assembly box 4 to an in the fuel element head, not shown.
  • the fuel assembly box 4 is in its lower area with other elements, in the example knobs 8b and outside plates 8c provided, which are specific to the exemplified box type. When such a fuel assembly box is conditioned, it is usually pressed and then cut into small pieces. However, such an approach is complex.
  • the invention is based on the object of specifying a method for disposing of a fuel assembly of a boiling water reactor system which is simplified compared to the procedure mentioned in the prior art.
  • the invention is based on the object of specifying a method for disposing of radioactively contaminated parts of a boiling water reactor system and an apparatus for carrying out this method.
  • the first-mentioned object is achieved according to the invention with a method having the features of claim 1.
  • the fuel assembly is stabilized with a support structure.
  • the fuel element box is not destroyed, but is provided with one or more components that support it, which give it greater strength or stability. This means that complex pressing and dismantling of the fuel assembly box is no longer necessary and disposal is simplified.
  • a fuel assembly prepared or conditioned in this way for disposal can also be used at the same time as a transport container for other parts to be disposed of and appropriately conditioned, in particular for core installation parts or for small-volume so-called gore scrap.
  • the fuel assembly box is provided with a handle.
  • the support structure is preassembled and inserted into the fuel assembly box.
  • the fuel assembly box is closed on one of its end faces with the aid of a base plate arranged on the support structure and serving as the base. In this way it can be used as a container for holding small-volume Gore scrap.
  • the object is achieved according to the invention with the features of claim 6. Since the stabilized fuel assembly is used as a transport container for other radioactive contaminated parts, its particularly cost-effective disposal together with the Gore scrap is possible.
  • the leaves are separated from a control element to be disposed of and inserted into the stabilized fuel assembly box. Since the longitudinal and transverse dimensions of the leaves of a control element largely correspond to those of a fuel assembly box, these can be accommodated in a space-saving manner in a fuel assembly box, which can accommodate the leaves of three control elements in this way.
  • the support structure divides the fuel assembly box with an internal partition into at least two parts. areas that are supported when the sheets are inserted into one of the partial areas. This makes it easier to fill the fuel assembly box.
  • La and b a plan view of the bottom side or on a long side of a fuel assembly box
  • FIG. 2a and b a plan view of the bottom side or on the long side of a support structure according to the invention
  • Fig. 3a and b a plan view of the front side or on a long side of the fuel assembly box stabilized with the support structure
  • 4a and b show a plan view of the end face or on a longitudinal side of the fuel assembly filled with the leaves of control rods.
  • the support structure 10 comprises a base plate 12 which carries a separating plate 14 which runs perpendicular to the flat side of the base plate and is in particular welded to it.
  • the separating plate 14 has a longitudinal dimension which is greater than the longitudinal dimension of the fuel assembly box 4 and is provided with a recess 16 at its free end facing away from the base plate 12, so that a carrying handle 18 is formed.
  • a spacer plate 20 is fastened to the base plate 12 and passes through the partition plate 14 provided with a slot 22 in this area.
  • FIGS. 3a, b show the fuel assembly 40 stabilized with the support structure 10. For this purpose, it is inserted into the empty fuel assembly 4 from the bottom side until the base plate 12 closes the empty fuel assembly 4 and forms a floor. The carrying handle 18 then protrudes beyond the fuel assembly box 4. In the figure it can also be seen that the fuel assembly 4 is divided into two sub-areas 42, 44 by the partition plate 14.
  • control rod blades 24 are introduced into the fuel assembly 40 stabilized with the support structure 10, which control rods 24 have been separated in a previous work step and from which control brackets 26 are halved in FIG. 4b by the previous disassembly a handle is located.
  • the spacer plate 20 serves to support the control rod leaves 24, so that the space used for accommodating the control rod leaves 24 is free from disturbing internals located in the lower region of the fuel assembly box 4.
  • four subchambers 46 are formed below the control rod blades 24, which can be used to hold small-volume core scrap. LIST OF REFERENCE NUMBERS

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (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)
  • Processing Of Solid Wastes (AREA)

Abstract

L'invention concerne un procédé pour éliminer une gaine d'éléments combustibles (4) dans une centrale nucléaire à réacteur à eau bouillante, selon lequel la gaine d'éléments combustibles (4) est stabilisée au moyen d'une structure porteuse (10). Ainsi, ladite gaine peut servir de conteneur pour transporter d'autres pièces à éliminer et conditionnées en conséquence, notamment des éléments nucléaires insérés dans le réacteur.
EP03759894A 2002-06-13 2003-05-22 Procede et dispositif pour eliminer une gaine d'elements combustibles dans une centrale nucleaire a reacteur a eau bouillante Expired - Lifetime EP1512155B1 (fr)

Applications Claiming Priority (3)

Application Number Priority Date Filing Date Title
DE10226245A DE10226245A1 (de) 2002-06-13 2002-06-13 Verfahren und Vorrichtung zum Entsorgen eines Brennelementkastens Entsorgen einer Siedewasserreaktoranlage
DE10226245 2002-06-13
PCT/EP2003/005339 WO2003107356A1 (fr) 2002-06-13 2003-05-22 Procede et dispositif pour eliminer une gaine d'elements combustibles dans une centrale nucleaire a reacteur a eau bouillante

Publications (2)

Publication Number Publication Date
EP1512155A1 true EP1512155A1 (fr) 2005-03-09
EP1512155B1 EP1512155B1 (fr) 2009-04-01

Family

ID=29719014

Family Applications (1)

Application Number Title Priority Date Filing Date
EP03759894A Expired - Lifetime EP1512155B1 (fr) 2002-06-13 2003-05-22 Procede et dispositif pour eliminer une gaine d'elements combustibles dans une centrale nucleaire a reacteur a eau bouillante

Country Status (6)

Country Link
EP (1) EP1512155B1 (fr)
JP (1) JP2005534003A (fr)
DE (2) DE10226245A1 (fr)
ES (1) ES2322648T3 (fr)
TW (1) TWI220992B (fr)
WO (1) WO2003107356A1 (fr)

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP5781265B2 (ja) * 2009-07-31 2015-09-16 三菱重工業株式会社 燃料集合体の輸送容器

Family Cites Families (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US5629964A (en) * 1994-03-11 1997-05-13 Roberts; Paul Neutron absorbing apparatus
DE19728978A1 (de) * 1997-07-07 1999-01-14 Siemens Ag Behälter für mehrere gebrauchte Brennelemente eines Kernreaktors
DE29912810U1 (de) * 1999-07-22 2000-11-23 Siemens AG, 80333 München Brennelementkasten mit Anschlag für Hebewerkzeug
DE19947120C2 (de) * 1999-09-30 2002-02-28 Framatome Anp Gmbh Verfahren zur Vorbereitung eines Brennelements für die Endlagerung und vorbereitetes Brennelement

Non-Patent Citations (1)

* Cited by examiner, † Cited by third party
Title
See references of WO03107356A1 *

Also Published As

Publication number Publication date
EP1512155B1 (fr) 2009-04-01
TW200402740A (en) 2004-02-16
ES2322648T3 (es) 2009-06-24
WO2003107356A1 (fr) 2003-12-24
DE10226245A1 (de) 2004-01-08
JP2005534003A (ja) 2005-11-10
TWI220992B (en) 2004-09-11
DE50311371D1 (de) 2009-05-14

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