CA1062451A - Fabrication method for mixed oxide fuel - Google Patents
Fabrication method for mixed oxide fuelInfo
- Publication number
- CA1062451A CA1062451A CA248,903A CA248903A CA1062451A CA 1062451 A CA1062451 A CA 1062451A CA 248903 A CA248903 A CA 248903A CA 1062451 A CA1062451 A CA 1062451A
- Authority
- CA
- Canada
- Prior art keywords
- fuel
- coarse
- fraction
- oxide
- fabrication method
- 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.)
- Expired
Links
- 239000000446 fuel Substances 0.000 title claims abstract description 30
- 238000000034 method Methods 0.000 title claims abstract description 25
- 238000004519 manufacturing process Methods 0.000 title claims abstract description 14
- 239000000463 material Substances 0.000 claims abstract description 12
- 238000005245 sintering Methods 0.000 claims abstract description 9
- 150000003839 salts Chemical class 0.000 claims abstract description 5
- 239000012798 spherical particle Substances 0.000 claims abstract description 5
- 239000007858 starting material Substances 0.000 claims abstract description 4
- 229910052778 Plutonium Inorganic materials 0.000 claims description 9
- 229910052770 Uranium Inorganic materials 0.000 claims description 5
- OYEHPCDNVJXUIW-UHFFFAOYSA-N plutonium atom Chemical compound [Pu] OYEHPCDNVJXUIW-UHFFFAOYSA-N 0.000 claims description 2
- ZCUFMDLYAMJYST-UHFFFAOYSA-N thorium dioxide Chemical compound O=[Th]=O ZCUFMDLYAMJYST-UHFFFAOYSA-N 0.000 claims description 2
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 claims description 2
- WZECUPJJEIXUKY-UHFFFAOYSA-N [O-2].[O-2].[O-2].[U+6] Chemical compound [O-2].[O-2].[O-2].[U+6] WZECUPJJEIXUKY-UHFFFAOYSA-N 0.000 claims 1
- 238000010438 heat treatment Methods 0.000 claims 1
- ZQPKENGPMDNVKK-UHFFFAOYSA-N nitric acid;plutonium Chemical compound [Pu].O[N+]([O-])=O ZQPKENGPMDNVKK-UHFFFAOYSA-N 0.000 claims 1
- 229910003452 thorium oxide Inorganic materials 0.000 claims 1
- 229910000439 uranium oxide Inorganic materials 0.000 claims 1
- 238000005470 impregnation Methods 0.000 abstract description 2
- 239000002245 particle Substances 0.000 description 6
- FLDALJIYKQCYHH-UHFFFAOYSA-N plutonium(IV) oxide Inorganic materials [O-2].[O-2].[Pu+4] FLDALJIYKQCYHH-UHFFFAOYSA-N 0.000 description 3
- 238000001311 chemical methods and process Methods 0.000 description 2
- 238000000975 co-precipitation Methods 0.000 description 2
- 238000009826 distribution Methods 0.000 description 2
- 239000000203 mixture Substances 0.000 description 2
- 239000003758 nuclear fuel Substances 0.000 description 2
- 238000012856 packing Methods 0.000 description 2
- ZSLUVFAKFWKJRC-IGMARMGPSA-N 232Th Chemical compound [232Th] ZSLUVFAKFWKJRC-IGMARMGPSA-N 0.000 description 1
- 229910002651 NO3 Inorganic materials 0.000 description 1
- NHNBFGGVMKEFGY-UHFFFAOYSA-N Nitrate Chemical compound [O-][N+]([O-])=O NHNBFGGVMKEFGY-UHFFFAOYSA-N 0.000 description 1
- 241000339283 Sphex Species 0.000 description 1
- 229910004369 ThO2 Inorganic materials 0.000 description 1
- 229910052776 Thorium Inorganic materials 0.000 description 1
- 239000011362 coarse particle Substances 0.000 description 1
- 239000000843 powder Substances 0.000 description 1
Classifications
-
- C—CHEMISTRY; METALLURGY
- C04—CEMENTS; CONCRETE; ARTIFICIAL STONE; CERAMICS; REFRACTORIES
- C04B—LIME, MAGNESIA; SLAG; CEMENTS; COMPOSITIONS THEREOF, e.g. MORTARS, CONCRETE OR LIKE BUILDING MATERIALS; ARTIFICIAL STONE; CERAMICS; REFRACTORIES; TREATMENT OF NATURAL STONE
- C04B38/00—Porous mortars, concrete, artificial stone or ceramic ware; Preparation thereof
-
- 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
Landscapes
- Engineering & Computer Science (AREA)
- Chemical & Material Sciences (AREA)
- Physics & Mathematics (AREA)
- Ceramic Engineering (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Materials Engineering (AREA)
- Structural Engineering (AREA)
- Organic Chemistry (AREA)
- Manufacturing & Machinery (AREA)
- Inorganic Compounds Of Heavy Metals (AREA)
Abstract
TITLE
FABRICATION METHOD FOR MIXED OXIDE FUEL
Inventor Melville A. Feraday ABSTRACT OF DISCLOSURE
A mixed oxide fuel fabrication method using a starting material of an oxide of a first fuel in the form of spherical particles of two size fractions, fine and coarse, the process comprising sintering the fine fraction to full density sintering the coarse fraction to a predeter-mined density such that the porosity will allow enrichment, impregnating the coarse fraction with a salt of a second fuel material and treating this fraction to convert the impregnating material to an oxide and then loading both fractions into a fuel element sheath and compacting. In the preferred process three size fractions are used i.e. fine, medium, and coarse with only the coarse-fraction being subject to the impregnation step.
FABRICATION METHOD FOR MIXED OXIDE FUEL
Inventor Melville A. Feraday ABSTRACT OF DISCLOSURE
A mixed oxide fuel fabrication method using a starting material of an oxide of a first fuel in the form of spherical particles of two size fractions, fine and coarse, the process comprising sintering the fine fraction to full density sintering the coarse fraction to a predeter-mined density such that the porosity will allow enrichment, impregnating the coarse fraction with a salt of a second fuel material and treating this fraction to convert the impregnating material to an oxide and then loading both fractions into a fuel element sheath and compacting. In the preferred process three size fractions are used i.e. fine, medium, and coarse with only the coarse-fraction being subject to the impregnation step.
Description
'` 106Z45I
This invention relates to a method of making .:
mixed oxide fuel elements.
A common method of making nuclear fuel elements is to take particles or spheres oE ~uel, load them into a sheath and vibratorily compact them to hlgh density. Generally three cizes of spheres are used, e.g. coarse (65%), medium (20~i) and fine (15~). For mixed oxide fuels the following powder fuel fabrication methods have been used: ;
?. a) The fuel is all made of the same composition, e~g.
lO (U-0.5 wt % Pu)O2 by co-precipitating the ~U,Pu)O2 spheres.
~,~ This has the disadvantages: (l) all the fuel has to be made Y in glove boxes (2) a co-precipitation process has to be used , ., which is more difficult than making spheres of one composition .~. ~ .. . .
(3) the chemical process which is difficult at the best of ~; times has to be done within the glove box area.
b) Some of the fuel is fabricated outside the confined ~ area as UO2~while the balance is either fabricated as PuO2 ;~ or (U, Pu)O2 sphéres . The two materials are then loaded together into~the sheath. In this case the enriching matexial 20 would be added as PuO2 particles or as co-precipitated ; particles ~U; Pu)O~ of one size fractions. This method has the following disadvantages: (l) if' pure PuO2 particles are used they ~ould have to be relatively small e.g. 40 ~m or hot spots could develop ln the element in use. Also it is di:Eficult .
to get a uniEorm distribution of enrichment along the element during sphere packing using fine enriched sphexes. (2) if (U, Pu)~2 particles are used the same difficulties as in (a~
,,j , .....
This invention relates to a method of making .:
mixed oxide fuel elements.
A common method of making nuclear fuel elements is to take particles or spheres oE ~uel, load them into a sheath and vibratorily compact them to hlgh density. Generally three cizes of spheres are used, e.g. coarse (65%), medium (20~i) and fine (15~). For mixed oxide fuels the following powder fuel fabrication methods have been used: ;
?. a) The fuel is all made of the same composition, e~g.
lO (U-0.5 wt % Pu)O2 by co-precipitating the ~U,Pu)O2 spheres.
~,~ This has the disadvantages: (l) all the fuel has to be made Y in glove boxes (2) a co-precipitation process has to be used , ., which is more difficult than making spheres of one composition .~. ~ .. . .
(3) the chemical process which is difficult at the best of ~; times has to be done within the glove box area.
b) Some of the fuel is fabricated outside the confined ~ area as UO2~while the balance is either fabricated as PuO2 ;~ or (U, Pu)O2 sphéres . The two materials are then loaded together into~the sheath. In this case the enriching matexial 20 would be added as PuO2 particles or as co-precipitated ; particles ~U; Pu)O~ of one size fractions. This method has the following disadvantages: (l) if' pure PuO2 particles are used they ~ould have to be relatively small e.g. 40 ~m or hot spots could develop ln the element in use. Also it is di:Eficult .
to get a uniEorm distribution of enrichment along the element during sphere packing using fine enriched sphexes. (2) if (U, Pu)~2 particles are used the same difficulties as in (a~
,,j , .....
2 and 3 above apply. ~;
` It is an object of the invention to provide ~--~, ~ 30 a mixed oxide nuclear fuel fabrication method that is simpler, ~-safer, and which -requires~ less processing in special environment than present methods. ;
; t . : ., . ` ~: .
~,~; :' ,!:: , . . ~. -1062~L5~
'` ' .
This and other objects of the invention are achieved b~ a mixed oxide fuel fabrication method using a starting material of an oxide of a first fuel in the form of spherical particles of two size ~ractions, fine and coarse, the process comprising sintering the fine fraction to full - . .
density, sintering the coarse ~raction to a predetermined -density such that the porosity will allow enrichment, impre-gnating the coarse fraction with a ~alt of a second fuel material and treating this fraction to convert the impregnating material to an oxide and then loading both fractions into a ~uel element. In the preferred process three size fractions J are used i.e. fine medium, and coarse with only the coarse ~; fraction being subject to the impregnation step.
An example of the process arrangement is as follows:
(a) the three size fractions of spheres are made as ` `
`~ U2 which can be made outside the glove box area.
b) the fine and medium spheres are sintered to full density (~ 97%) thoeretical density (TD).
~c~ the coarse spheres are partially sintered to a suitable density e.g. 80% leaving enough porosity for the next step. As an alternative fully sintered spheres :~ . .
containing stable porosity could be used.
~d) the coarse spheres are impregnated with a Pu nitrate solution to get the required enrichment (e.g. U-l wt% Pu) ~: .
and then sintered to ~ull density. I the alternative method (c above) is used then the spheres would~'just be ... . .
heat treated to convert the impregnant to an oxide.
(e) the spheres~are then all loaded into the sheath and 3a compacted to the desired packing density.
This xoute offers the following advantages-compared with the normal routes.
s ~
'~. .
.. . . .
~. : - . . - , `` lQ6245~ ~
(i~ most o~ the camplica~ed chemlcal processes are done outside the glove boxes.
(ii) co-precipitation of U and Pu would not be required i.e. a simpler chemical process would be used. ~ -(iii) because the coarse particles contain the enrichment it would not be possible to get enough enrichment ~ segre~ated in an element to get a hot spot.
,'! (iV) recycle of reject UO2 spheres could be done readily.
Although this method is particularly interestlng for (Uj Pu)O2 fuels because of the dif~lculty of forming (U,Pu)O2 spheres at high yield rates, it should be applicable to the thorium cycle as well. In this arrangement ThO2 would be enriched with an enriching salt~of~plutonium ~;;
or uranium.
In the above description spherical particles are dlscussed. This should be construed to cov~r the use of shard particles and similar size ~raction as well.
Typical size fraction distribution is as follows: :
~ ~ Coarse ~......... 700-lOOO ~m Medlum.......... 100-200 ~m Fine .. ,.............. 20-40 t~ "' ' ,!1 ,. .
. 1 . .. .
V ', " ' ' `~.: ':
'.'.'
` It is an object of the invention to provide ~--~, ~ 30 a mixed oxide nuclear fuel fabrication method that is simpler, ~-safer, and which -requires~ less processing in special environment than present methods. ;
; t . : ., . ` ~: .
~,~; :' ,!:: , . . ~. -1062~L5~
'` ' .
This and other objects of the invention are achieved b~ a mixed oxide fuel fabrication method using a starting material of an oxide of a first fuel in the form of spherical particles of two size ~ractions, fine and coarse, the process comprising sintering the fine fraction to full - . .
density, sintering the coarse ~raction to a predetermined -density such that the porosity will allow enrichment, impre-gnating the coarse fraction with a ~alt of a second fuel material and treating this fraction to convert the impregnating material to an oxide and then loading both fractions into a ~uel element. In the preferred process three size fractions J are used i.e. fine medium, and coarse with only the coarse ~; fraction being subject to the impregnation step.
An example of the process arrangement is as follows:
(a) the three size fractions of spheres are made as ` `
`~ U2 which can be made outside the glove box area.
b) the fine and medium spheres are sintered to full density (~ 97%) thoeretical density (TD).
~c~ the coarse spheres are partially sintered to a suitable density e.g. 80% leaving enough porosity for the next step. As an alternative fully sintered spheres :~ . .
containing stable porosity could be used.
~d) the coarse spheres are impregnated with a Pu nitrate solution to get the required enrichment (e.g. U-l wt% Pu) ~: .
and then sintered to ~ull density. I the alternative method (c above) is used then the spheres would~'just be ... . .
heat treated to convert the impregnant to an oxide.
(e) the spheres~are then all loaded into the sheath and 3a compacted to the desired packing density.
This xoute offers the following advantages-compared with the normal routes.
s ~
'~. .
.. . . .
~. : - . . - , `` lQ6245~ ~
(i~ most o~ the camplica~ed chemlcal processes are done outside the glove boxes.
(ii) co-precipitation of U and Pu would not be required i.e. a simpler chemical process would be used. ~ -(iii) because the coarse particles contain the enrichment it would not be possible to get enough enrichment ~ segre~ated in an element to get a hot spot.
,'! (iV) recycle of reject UO2 spheres could be done readily.
Although this method is particularly interestlng for (Uj Pu)O2 fuels because of the dif~lculty of forming (U,Pu)O2 spheres at high yield rates, it should be applicable to the thorium cycle as well. In this arrangement ThO2 would be enriched with an enriching salt~of~plutonium ~;;
or uranium.
In the above description spherical particles are dlscussed. This should be construed to cov~r the use of shard particles and similar size ~raction as well.
Typical size fraction distribution is as follows: :
~ ~ Coarse ~......... 700-lOOO ~m Medlum.......... 100-200 ~m Fine .. ,.............. 20-40 t~ "' ' ,!1 ,. .
. 1 . .. .
V ', " ' ' `~.: ':
'.'.'
Claims (6)
1. A mixed oxide fuel fabrication method using a starting material of an oxide of a first fuel in the form of spherical particles two size fractions, fine, and coarse, the process comprising sintering the fine fraction to full density, sintering the coarse fraction to a predetermined density such that the porosity will allow enrichment, impregnating the coarse fraction with an enriching salt of a second fuel material and treating this fraction to convert the impregnating material to an oxide and then loading both fractions into a fuel element sheath and compacting.
2. A mixed oxide fuel fabrication method using a starting material of an oxide of a first fuel in the form of spherical particles of three size fractions, fine, medium and coarse, the process comprising sintering the fine and medium fractions to full density, sintering the coarse fraction to a predetermined density such that the porosity will allow enrichment, impregnating the coarse fraction with an enriching salt of a second fuel material and treating this fraction to convert the impregnating material to an oxide and then loading all three fractions into a fuel element sheath and compacting.
3. A mixed oxide fuel fabrication method as in claim 1 or claim 2 wherein the starting first fuel is uranium oxide and the imprognating material is plutonium nitrate.
4. A mixed oxide fuel fabrication method as in claim 1 or claim 2 wherein the starting first fuel is thorium oxide and the impregnating material is salt of plutonium or uranium.
5. A mixed oxide fuel fabrication method as in claim 1 or claim 2 wherein the sintering of the coarse fraction is done in two stages with the imprignating step being done between stages.
6. A mixed oxide fuel fabrication method as in claim 1 or claim 2 wherein the treating of the coarse fraction to convert the impregnating material to an oxide is carried out by heat treatment.
Priority Applications (4)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CA248,903A CA1062451A (en) | 1976-03-26 | 1976-03-26 | Fabrication method for mixed oxide fuel |
| SE7701018A SE7701018L (en) | 1976-03-26 | 1977-02-01 | WAY TO PRODUCE A MIXED OXIDE FUEL |
| FR7704957A FR2345790A1 (en) | 1976-03-26 | 1977-02-21 | METHOD OF MANUFACTURING A NUCLEAR FUEL BASED ON MIXED OXIDES |
| GB8572/77A GB1545658A (en) | 1976-03-26 | 1977-03-01 | Fabrication method for mixed oxide nuclear fuel |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CA248,903A CA1062451A (en) | 1976-03-26 | 1976-03-26 | Fabrication method for mixed oxide fuel |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CA1062451A true CA1062451A (en) | 1979-09-18 |
Family
ID=4105562
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CA248,903A Expired CA1062451A (en) | 1976-03-26 | 1976-03-26 | Fabrication method for mixed oxide fuel |
Country Status (4)
| Country | Link |
|---|---|
| CA (1) | CA1062451A (en) |
| FR (1) | FR2345790A1 (en) |
| GB (1) | GB1545658A (en) |
| SE (1) | SE7701018L (en) |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| GB9901284D0 (en) * | 1999-01-22 | 1999-03-10 | British Nuclear Fuels Plc | Fuel fabrication |
Family Cites Families (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| GB1159520A (en) * | 1967-09-25 | 1969-07-30 | Grace W R & Co | Process for preparing multi-component nuclear fuels |
| US3789013A (en) * | 1967-09-25 | 1974-01-29 | Grace W R & Co | Process for preparing multi-component nuclear fuels |
| CA872722A (en) * | 1968-06-17 | 1971-06-08 | Pawliw John | Preparation of mixed oxide nuclear fuel |
| BE813383A (en) * | 1974-04-05 | 1974-07-31 | Uranium oxide-plutonium oxide mixtures - made from solid soln. mixed with uranium oxide |
-
1976
- 1976-03-26 CA CA248,903A patent/CA1062451A/en not_active Expired
-
1977
- 1977-02-01 SE SE7701018A patent/SE7701018L/en unknown
- 1977-02-21 FR FR7704957A patent/FR2345790A1/en active Granted
- 1977-03-01 GB GB8572/77A patent/GB1545658A/en not_active Expired
Also Published As
| Publication number | Publication date |
|---|---|
| SE7701018L (en) | 1977-09-27 |
| GB1545658A (en) | 1979-05-10 |
| FR2345790B1 (en) | 1980-04-25 |
| FR2345790A1 (en) | 1977-10-21 |
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