WO1998010428A1 - Kernreaktor-brennelement mit hohem abbrand und verfahren zu seiner fertigung - Google Patents
Kernreaktor-brennelement mit hohem abbrand und verfahren zu seiner fertigung Download PDFInfo
- Publication number
- WO1998010428A1 WO1998010428A1 PCT/EP1997/004652 EP9704652W WO9810428A1 WO 1998010428 A1 WO1998010428 A1 WO 1998010428A1 EP 9704652 W EP9704652 W EP 9704652W WO 9810428 A1 WO9810428 A1 WO 9810428A1
- Authority
- WO
- WIPO (PCT)
- Prior art keywords
- powder
- fuel
- pellets
- enriched
- poisoned
- Prior art date
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
- G21C3/02—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
- G21C3/42—Selection of substances for use as reactor fuel
- G21C3/58—Solid reactor fuel Pellets made of fissile material
- G21C3/62—Ceramic fuel
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C21/00—Apparatus or processes specially adapted to the manufacture of reactors or parts thereof
- G21C21/02—Manufacture of fuel elements or breeder elements contained in non-active casings
-
- 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
- G21C3/42—Selection of substances for use as reactor fuel
- G21C3/58—Solid reactor fuel Pellets made of fissile material
- G21C3/62—Ceramic fuel
- G21C3/623—Oxide fuels
-
- 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 method for producing a nuclear reactor fuel element with high burn-up, that is to say, for example, a nuclear reactor fuel element with a burning time of 5 or more cycles, and a corresponding enrichment of fissile material which corresponds to more than 5% U 23 s.
- the invention is based on a manufacturing method that has the features of the preamble of claim 1.
- the uranium of the uranium compound contains natural uranium (mainly the uranium isotope U 3 ⁇ that cannot be used directly for the chain reaction of the reactor) and the uranium isotope U 235 , which is important for the chain reaction, with the U235 content for safety reasons. This is the "enrichment”, is generally limited and in any case must not exceed a maximum value (generally 5%).
- the oxide powder which is generated, for example, from UF 6 by reduction in an H 2 / H 2 0 gas, is filled into the transport containers T1, T2,... Tn in a filling station 2, the volume the transport container Tl, T2, ... Tn is relatively small (for example, only for 100 kg of U0 2 powder), that is to say in each case only comprises a subcritical amount of fissile material and is also provided with rods S and / or a lining made of neutron-absorbing material.
- the production plant comprises a first part 3 with a powder store and devices for powder processing, of which only one powder mixer M is shown in Fig. 1, e.g. a large mixing container with a stirring device, at the bottom of which a powder mixture is drawn off, which consists of the carefully homogenized contents of the transport containers Tl, T2, ... Tn emptied into the powder mixer M.
- This powder mixture can e.g. are conveyed (e.g. sucked in or blown with compressed air) via a powder feed line and other devices of the first part into the second part of the production system.
- Samples of the powder mixture are constantly examined at an analysis station 4 in order to control the homogeneity, fissile enrichment and quality of the mixture.
- the facilities of this first part of the production plant are designed with regard to their capacity so that they can hold so much powder that a filling of highly enriched material would come into dangerous proximity to the critical mass and would no longer be safe to handle. For security reasons, therefore, is a maximum value for €? Enrichment (eg 5%) is specified, and the capacity of the production facilities is designed so that the fissile material does not reach the critical mass, ie can be safely handled, even at the highest permitted enrichment value.
- the volume and criticality dimensioning of the powder mixer M is usually designed for 1 to 4 tons, so that even a filling made from a non-poisoned powder Mixing with the permitted maximum value of, for example, 5% U 23 5 cannot come close to the critical mass.
- This powder mixture is processed further in the second part of the production plant, a pellet press producing 5 pellet green compacts which are sintered in a sintering furnace 6.
- these pellets are ground to their final shape, measured, weighed and finally enclosed in a filling station 8 in corresponding metallic cladding tubes H, which usually consist of zirconium alloy (e.g. Zirkaloy).
- An assembling station 9 places these filled cladding tubes, which are gas-tightly welded by means of metallic end pieces, i.e. the fuel rods (FR), and other structural parts S of the fuel assembly, such as e.g. Head pieces, foot pieces and spacers as well as guide tubes or fuel boxes, together to form the finished fuel assembly ("fuel assembly", FA).
- “poisoned fuel assemblies” are also used to replace some of the spent fuel assemblies in a pressurized water reactor.
- these "poisoned fuel elements” contain a combustible neutron absorber, that is to say an absorber material whose absorption capacity for thermal neutrons decreases with increasing service life in the reactor.
- This "combustible neutron poison” neutralizes some of the neutrons emanating from the enriched material through nuclear fission, but the absorption effect has already decayed after one operating cycle to a residual, practically negligible absorption capacity.
- the production of poisoned fuel elements is shown schematically in FIG. 2.
- the relatively expensive burnable neutron poison usually gadolinium oxide Gd 2 ⁇ is only added to a few pellets of a fuel element, the powder mixture of which is produced in a special part of the production system, while the conversion system 1, the filling station 2, and the devices with the powder mixer M
- the powder mixture of the other pellets is used and the second part of the production plant can be used together with the pellet press 5, the sintering furnace 6, the quality level 7, the filling station 8 and the assembly stage 9
- fuel powder of the poisoned pellets is removed from transport containers V, which come from a conversion system 10.
- lver is generally first filled into the transport container V in a filling station 11 and then Homogenization of the mixture fed to a tumble mixer 12.
- Niobium (3 ⁇ to 6 ⁇ m thick) is charged, on which .ZrB 2 is then chemically separated from the vapor phase.
- boron glass spiders steel tubes filled with boron glass can be inserted into the guide tubes of fuel assemblies via their own holders (so-called "boron glass spiders"), which are not required to control reactor operation and into which no control rods are therefore inserted.
- boron-containing microparticles eg from ZrB
- a coating e.g. made of molybdenum
- Spent fuel assemblies still contain fissile plutonium, which can be separated from the spent fissile material in appropriate reprocessing plants in order to use it instead of fissile U235 to enrich fissile material for fresh fuel elements.
- fissile plutonium For the production of fuel elements from such mixed oxide (MOX, i.e. mixture of uranium oxide and plutonium oxide), devices of the special part of the production plant shown in FIG. 2 are used.
- the transport container P (FIG.
- Highly enriched fuel can namely. B. only m
- a further limitation of the enrichment arises from the requirement that the finished fuel elements must also be sufficiently removed from the critical act if they (unintentionally in the distribution center or during transport) are inadvertently straight into the vicinity of larger quantities of water (eg quenching water) in case of fire). Therefore, common fuel elements of the type 16 x 16 or 18 x 18 must not have an enrichment of more than 4.4% (for the type 17 x 17 the limit is somewhat higher). Safety would also be ensured if larger amounts of absorber material were installed in the structure of the fuel assembly. However, this either necessitates fundamental changes in the structure or structural material of the fuel elements, or special pellets containing absorber must be used. There are currently no concepts for either route that can be implemented quickly and economically. Rather, attempts are being made to extend the service life of the fuel elements without exceeding the enrichment limits by making better use of the previously available burn-up potential.
- the invention is therefore based on the object of providing a method for producing fuel elements with such a highly enriched fissile material and of specifying corresponding fuel elements at all without lengthy and complex changes to the prior art having to be made.
- the invention is based on the fact that basically the enrichment of the fissile core material itself, but only its reactivity and the reactivity of the finished fuel elements is the safety-relevant parameter. Instead of starting from the complete enrichment of the fissile material in order to maintain safety, it makes physical sense to subtract from this enrichment that part which may be compensated for by already added combustible neutron poison. It should therefore be based on the reactivity of the powder used, the resulting pellet and the fuel assembly. For the processing of a non-poisoned powder mixture, reactivity and enrichment are equivalent, and for the handling previously considered safe, the system according to FIG. 1 can still only be used with fissile material whose enrichment does not exceed the maximum value, for example 5% .
- a powder mixture is processed with the same degree of security, in which the enrichment of the fissile material is above this maximum value, but the powder mixture also contains an amount such that the reactivity of the latter the poisoned powder mixture corresponds to the reactivity of a non-poisoned powder mixture, the accumulation of which does not exceed the maximum value mentioned.
- the corresponding pellets then have the required lower reactivity, although they have a higher concentration ("burn-off potential").
- FIG 3 schematically shows the method steps and devices used for an embodiment of the method according to the invention.
- the transport containers T, P and N which are supplied by the conversion system or reprocessing system and are filled with enriched fissile material, plutonium-containing powder and powder with natural uranium, or in some other way contain the enriched fissile material.
- Cladding tubes H and the other structural parts required for the production of the fuel elements are also kept ready. Furthermore, a supply of absorber material is also assumed, e.g. can consist of gadolinium oxide according to the prior art.
- the fuel powder to be processed in the pellet press is produced by a powder mixture in the powder mixer M. is produced, which on the one hand contains fissile material with an enrichment above the maximum enrichment value. On the other hand, this powder mixture contains such an amount of absorber material that the reactivity of the powder mixture has at most the reactivity that is equivalent to the reactivity of an unconfirmed, enriched fissile material.
- 3 can of course be a mixture of plutonium oxide, natural (or depleted) uranium oxide and enriched uranium oxide, but it is also possible to use only depleted uranium oxide and plutonium oxide, only enriched uranium oxide or another suitable cleavage material.
- This stock of highly enriched fission material can in particular be easily managed if the material is filled into many individual containers, the volume of which is only a fraction of the capacity of the powder mixer M.
- These containers can in particular consist of an absorber-containing material and / or contain additional absorbent components. The absorber material is mixed homogeneously with the contents of several such containers in the powder mixer.
- the absorber material can be present in the conventional way as gadolinium oxide, which can be mixed with the powder of the cleavage material, pressed into pellets and sintered in a known manner, directly or after additional measures for granulating and producing desired grain sizes. Tests on a laboratory scale have also shown favorable behavior during mixing, pressing and sintering for powders made of ZrB 2 particles which are coated with molybdenum and mixed with uranium oxide powder. The burning behavior of boron particularly meets the requirements placed on the absorber by highly enriched fuel elements designed for a long period of use. Borides of rare earths such as gadolinium, erbium, euroblum, samarium etc. or hafnium are similarly also is suitable.
- Absorbent powders containing metal also appear to be suitable. It is particularly advantageous to use not only one neutron absorbing chemical element, but several elements, in particular two elements. "Double absorbers" such as GdB 2 , GdB or GdB 6 allow MOX fuel elements with an increased content of fissile plutonium to be produced. Not only can the storage properties of the fresh fuel and the fresh fuel elements, but also the behavior of the fuel elements in the reactor be favorably influenced.
- Standard dimensions and standard materials can be used for the cladding tubes and structural parts.
- hafnium contents are usually prescribed for reactor materials, hafnium contents of up to 2% are quite possible here. This saves further costs because e.g. Zirconium sponge (the most common base metal for alloys used in nuclear technology) can only be cleaned of hafnium in a complex manner.
- the fuel assemblies are not only in the planes in which the fuel rod is attached for mechanical reasons Spacer grids must be supported, but also contain grids in intermediate levels. These intermediate grids are then provided with mixing devices in order to obtain better cooling of the highly enriched fuel rod by mixing the coolant.
- the enveloping tubes are particularly corrosion-resistant, for example, consist of a mechanically stable tube made of a zirconium alloy and contain a thin coating of a corrosion-resistant material on the outer surface exposed to the coolant, as described in the European patent
- the fuel element is adapted to a long period of use not only with regard to its energy content and the enrichment of fissile material, but also with regard to the other chemical and physical conditions.
- pellets with impermissibly high enrichment are produced in the production lines (3 to 9), which are designed for processing large quantities of normally enriched fuel, the impermissible enrichment being compensated for by the fact that already in the powder mixer (M) at the entrance of the production line so much absorber material (U / B powder) is mixed to the fuel (T, P, N) that the reactivity of the poisoned mixture is the reactivity of an unpoisoned one
- Fuel mixture does not exceed normal enrichment.
- Corresponding fuel assemblies then contain larger quantities of these poisoned pellets (or - if necessary in addition to the neutral pellets mentioned - only those poisoned pellets) which are produced in large numbers (and therefore economically) with the conventional systems.
- Enriched fission material and an absorber material are then converted into poisoned pellets for the production of such fuel elements pressed and, if necessary, neutral pellets made from non-enriched material that is practically non-fissile (e.g. natural uranium or depleted uranium).
- These pellets are placed in columns, which consist exclusively of such poisoned pellets and possibly still neutral pellets and are enclosed in metallic cladding tubes. In this way, fuel rods are created, which are then assembled together with the structural parts (possibly also control rod guide tubes or water-filled rods, but without the use of unggi ted fuel rods) to form the fuel assembly.
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- Engineering & Computer Science (AREA)
- Physics & Mathematics (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Chemical & Material Sciences (AREA)
- Ceramic Engineering (AREA)
- Manufacturing & Machinery (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Inorganic Compounds Of Heavy Metals (AREA)
Abstract
Description
Claims
Priority Applications (3)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP10512192A JP2000502809A (ja) | 1996-09-09 | 1997-08-26 | 高燃焼度の原子炉燃料要素およびその製造方法 |
EP97942878A EP0948794A1 (de) | 1996-09-09 | 1997-08-26 | Kernreaktor-brennelement mit hohem abbrand und verfahren zu seiner fertigung |
US09/863,684 US20010022827A1 (en) | 1996-09-09 | 2001-05-23 | Nuclear reactor fuel assembly with a high burnup |
Applications Claiming Priority (2)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
DE19636563.5 | 1996-09-09 | ||
DE19636563A DE19636563C1 (de) | 1996-09-09 | 1996-09-09 | Kernreaktor-Brennelemente mit hohem Abbrand und Verfahren zu ihrer Fertigung |
Related Child Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
US26515699A Continuation | 1996-09-09 | 1999-03-09 |
Publications (1)
Publication Number | Publication Date |
---|---|
WO1998010428A1 true WO1998010428A1 (de) | 1998-03-12 |
Family
ID=7805048
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
PCT/EP1997/004652 WO1998010428A1 (de) | 1996-09-09 | 1997-08-26 | Kernreaktor-brennelement mit hohem abbrand und verfahren zu seiner fertigung |
Country Status (7)
Country | Link |
---|---|
US (1) | US20010022827A1 (de) |
EP (1) | EP0948794A1 (de) |
JP (1) | JP2000502809A (de) |
KR (1) | KR20000068512A (de) |
DE (1) | DE19636563C1 (de) |
TW (1) | TW392178B (de) |
WO (1) | WO1998010428A1 (de) |
Families Citing this family (6)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US7139360B2 (en) * | 2004-10-14 | 2006-11-21 | Westinghouse Electric Co. Llc | Use of boron or enriched boron 10 in UO2 |
JP4772743B2 (ja) * | 2007-05-15 | 2011-09-14 | 株式会社東芝 | 原子燃料サイクル施設の臨界管理法 |
WO2009128250A1 (ja) * | 2008-04-16 | 2009-10-22 | 株式会社 東芝 | 原子燃料ペレットの製造方法、燃料集合体とその製造方法およびウラン粉末 |
FR2953637B1 (fr) | 2009-12-04 | 2012-03-23 | Commissariat Energie Atomique | Crayon de combustible nucleaire et procede de fabrication de pastilles d'un tel crayon |
RU2496164C1 (ru) * | 2012-07-24 | 2013-10-20 | Федеральное государственное унитарное предприятие "Научно-исследовательский институт Научно-производственное объединение "ЛУЧ" (ФГУП "НИИ НПО "ЛУЧ") | Способ формирования топливного сердечника стержневого тепловыделяющего элемента |
SI3364418T1 (sl) * | 2017-02-21 | 2021-08-31 | Westinghouse Electric Sweden Ab | Sintrana peleta jedrskega goriva, gorivna palica, gorivni sestav in postopek izdelave sintrane pelete jedrskega goriva |
Citations (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CH454291A (de) * | 1965-12-03 | 1968-04-15 | Westinghouse Electric Corp | Verfahren zum Herstellen von Brennstofftabletten |
EP0026389A1 (de) * | 1979-09-28 | 1981-04-08 | Kraftwerk Union Aktiengesellschaft | Verfahren zur Herstellung von hochdichten oxidischen Kernbrennstoffkörpern |
US4774051A (en) * | 1986-03-24 | 1988-09-27 | Kraftwerk Union Aktiengesellschaft | Sintered nuclear fuel compact and method for its production |
WO1997006535A1 (en) * | 1995-08-03 | 1997-02-20 | British Nuclear Fuels Plc | Nuclear fuel pellets |
Family Cites Families (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US3427222A (en) * | 1965-10-15 | 1969-02-11 | Westinghouse Electric Corp | Nuclear fuel elements |
DE1279230B (de) * | 1967-03-11 | 1968-10-03 | Kernenergieverwert Ges Fuer | Brennelementstab zum Aufbau von Reaktorkernen |
DE3402192A1 (de) * | 1983-02-22 | 1984-08-23 | Westinghouse Electric Corp., Pittsburgh, Pa. | Mit einem abbrennbaren neutronenabsorber beschichteter kernbrennstoffkoerper |
US4880597A (en) * | 1987-08-05 | 1989-11-14 | Combustion Engineering, Inc. | Alloy coated fuel cladding |
JP2928606B2 (ja) * | 1990-08-29 | 1999-08-03 | 株式会社日立製作所 | 燃料集合体 |
-
1996
- 1996-09-09 DE DE19636563A patent/DE19636563C1/de not_active Expired - Fee Related
-
1997
- 1997-08-26 KR KR1019997001930A patent/KR20000068512A/ko not_active Application Discontinuation
- 1997-08-26 JP JP10512192A patent/JP2000502809A/ja active Pending
- 1997-08-26 EP EP97942878A patent/EP0948794A1/de not_active Withdrawn
- 1997-08-26 WO PCT/EP1997/004652 patent/WO1998010428A1/de not_active Application Discontinuation
- 1997-08-28 TW TW086112372A patent/TW392178B/zh not_active IP Right Cessation
-
2001
- 2001-05-23 US US09/863,684 patent/US20010022827A1/en not_active Abandoned
Patent Citations (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CH454291A (de) * | 1965-12-03 | 1968-04-15 | Westinghouse Electric Corp | Verfahren zum Herstellen von Brennstofftabletten |
EP0026389A1 (de) * | 1979-09-28 | 1981-04-08 | Kraftwerk Union Aktiengesellschaft | Verfahren zur Herstellung von hochdichten oxidischen Kernbrennstoffkörpern |
US4774051A (en) * | 1986-03-24 | 1988-09-27 | Kraftwerk Union Aktiengesellschaft | Sintered nuclear fuel compact and method for its production |
WO1997006535A1 (en) * | 1995-08-03 | 1997-02-20 | British Nuclear Fuels Plc | Nuclear fuel pellets |
Also Published As
Publication number | Publication date |
---|---|
EP0948794A1 (de) | 1999-10-13 |
DE19636563C1 (de) | 1998-03-26 |
TW392178B (en) | 2000-06-01 |
US20010022827A1 (en) | 2001-09-20 |
KR20000068512A (ko) | 2000-11-25 |
JP2000502809A (ja) | 2000-03-07 |
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