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CA1200374A - Method for the manufacture of nuclear fuel products - Google Patents

Method for the manufacture of nuclear fuel products

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Publication number
CA1200374A
CA1200374A CA000436352A CA436352A CA1200374A CA 1200374 A CA1200374 A CA 1200374A CA 000436352 A CA000436352 A CA 000436352A CA 436352 A CA436352 A CA 436352A CA 1200374 A CA1200374 A CA 1200374A
Authority
CA
Canada
Prior art keywords
binder
fuel material
particulate
amine
nuclear fuel
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
Application number
CA000436352A
Other languages
French (fr)
Inventor
John D. Connolly, Jr.
Timothy J. Gallivan
Richard P. Ringle
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.)
General Electric Co
Original Assignee
General Electric Co
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 General Electric Co filed Critical General Electric Co
Priority to CA000436352A priority Critical patent/CA1200374A/en
Application granted granted Critical
Publication of CA1200374A publication Critical patent/CA1200374A/en
Expired legal-status Critical Current

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    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

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Abstract

METHOD FOR THE MANUFACTURE
OF NUCLEAR FUEL PRODUCTS

ABSTRACT OF THE DISCLOSURE
Nuclear fuel pellets are manufactured from coherent compacts in which the particulate ceramic nuclear fuel material is rendered more plastic, and amenable to processing by blending with a fugitive binder selected from a multi-functional primary amine group consisting of ethylene diamine; 3.3 diaminodipropylamine, 1.3 diaminopropane, 1.6 diaminohexane, 1.7 diaminoheptane, diethylene-triamine, and 3-dimethylaminopropylamine, thereafter introducing carbon dioxide gas into the blend, and pressing the resultant mix into the desired coherent compact.

Description

3~

METHOD FOR THE MANUFACTURE OF
NUCLEAR FUEL PRODUCTS
FIELD OF THE INVENTION

, This invention relates generally to the ceramic art and the formation of sintered bodies from particulate oxide materials. It is particularly concerned with a process for producing consolidated units of particulate ceramic materials including the compressing of such particles into coherent and handleable compacts for subsequent sintering to integrated bodies. The invention is specifically directed to the manufacture of nuclear fuel products from particulate materials containing uranium dioxide.
_ROSS-REFE~ENCE
This invention is related to that disclosed and claimed in Canadian Patent Application Serial No. 416,427 filed November 25, 1982, in the names of George L. Gaines, Jr., Patricia A. Piacente, William J. Ward III, Peter C.
Smith, Timothy J. Gallivan, and Harry M. Laska; and to Canadian Application Serial No 404,023 filed May 28, 1982, in the names of George L. Gaines, Jr. and William J. Ward III.
BACKGROUND OF THE INVENTION
-Fissionable nuclear fuel for nuclear reactors comprises a variety of compositions and forms of ; fissionable materials, including ceramic compounds of uranium, plutonium and thorium. Fuel compounds for ~ 25 commercial power generating reactors typically comprise ::

~UC~37~

oxides of uranium, plutonium and thorium, and mixtures thereof. The generally most suita~le and commonly used fuel for such commercial nuclear reactors is uranium dioxide, which can be combined with minor amounts of other fuel materials including neutron flux controlling additives such as gadolinium.
Commercially produced uranium dioxide is a fine, fairly porous powder, a form which is not suitable as such for use as fuel in commercial reactos. A number of means have been developed and used to convert powdered uranium dioxide into a form suitable for use as a fuel for in power generating nuclear reactors. One commonly used technique has been to sinter appropriately sized bodies of the powdered uranium dioxide material at high tem-peratures to develop strong di~Eusion bonds between theindividual powder particles.
However~ the sintering technique requires a preliminary forming of the loose powder into a shaped, and self-retaining, body of particles of sufficient strength and integrity to survive handling and the sintering procedure. The operation of consolidating fine particles into a body or coherent compact with accepta~le low levels of rejects, and the strength and uniformity ~or enduring subsequent handling and firing has been a subject of considerable concern and investigation in the nuclear fuel industry.
Conventional organic or plastic binders commonly used in powder fabrication have been considered to be unsuitable in nuclear fuel processing operations.
Entrainment of any binder residues such as carbon within the sintered nuclear fuel product is unacceptable in reactor service. Moreover/ the presence of any organic binder among the particles inhibits the formation during sintering of stror.g diffusion bonds between the particles, and adversely affects the density of the sintered product.

6~3'7~
2~-~F-04540 The complete removal of binders, or their decomposition products, prior ~o slntering is especially difficult~ and usually re~uires a costly additional operation in the fuel manufacture.
Accordingly, a common method has been to die press uranium dioxide powaer into appropriately si~ed "green"
(unfiredl compacts without the assistance of any binder.
This approach however has resulted in very costly high rates of rejects and scrap material recycling because of the weakness of green, binder-free compacts of powder.
U.S. Patent No. 4,061,700, issued December 6, 1977, to Gallivan, and assigned to to the same assignee as this application, discloses a distinctive group of ~ugitive binders that improved the production of sintered pellets of particulate nuclear fuel materials for nuclear reactors.
The fugitive binders of this patent function without contaminating the resulting fuel products, and they permit the formation of strong bonds between sintered particles during firing without deleteriously affecting the desired porosity of the sintered pellet.
The disclosure of the said U.S. Patent No. 4,061,700 and of U.S. Patent Nos. 3!803,273 to Hill et al dated April ~, 1974, 3,923,933 to Lay dated December 2, 1975 and U.S. 3,927,154 to Carter datèd December 16, 1975, also assigned to the same assignee as the instant application, and relating to significant aspects in the subject field o~ producing nucleax fuel pellets from particulate fissionable ceramic mater;al for reactor service.
The prior art techniques or means such as disclosed in U.S. Patent No. 4,061~700, have been found wanting in some conditions and circumstances. For instance it has been observed that the fugitive binders of the aforesaid patent do not provide consistent results as to pellet strength and integrity irrespective of the blending conditions and particle characteristics o~ the uranium dioxide powder. Specifically the severity of agitation .

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24-NF-0~5~0 in blending, relative humidity and temperature, and duration of storage, as well as the uranium oxide powder properties such as size, surface area and moisture content are all factors that apparently can detract from the uniformity of the physical attributes provided by such fugitive binders.
The amine-type of fugitive binder of the aforesaid applications Serial Nos 416,427 and 404,023 have been found to pro~ide significant improvements in the processing characteristic of particulate ceramic materials comprising uranium dioxide and in the physical properties of compacts formed therefrom.
Nevertheless, the foregoing prior art measures have not sufficiently overcome the inherent brittle nature of some ceramic materials comprising uranium dioxide powder and imparted therein a degree of plasticity to enable their consistent and rapid consolidation to coherent compacts having high resistance to fracture.
This invention deals with the typical brittle nature of ceramic materials and problems imposed thereby when compression molding such in materials in particulate form and also occurring in the resulting molded product.
As is well know, ceramic materials are generally of a relatively brittle consistency as opposed to a plastic conformable consistency. Thus, rather than gradually deforming over a period of progressively increasing applied compressive stress approaching the breaking point as is the case with a plastic material, ceramics tend to rigidly resist substantially all deformation until the breaking point is reached whereupon they abruptly fracture with the resulting fissure or fissures instantly progressing through the mass fragmenting it. ~1 apt illustration of this brittle and unyielding property and the facture characteristies of a ceramie is the erushing of a glass marble. On the other hand, a plastic material will gradually yield and deform with progressively increasing compressive .Z~ 3~a stress until reaching its breaking point and rupturing, and commonly the propagation of the resulting fracture is of a slower rate and does not continue to the extent of fragmenting the mass~ Thus, a plastic type of material is more ameable to compression molding than the brittle type of materïals.
This inherent ~rittle characteristic in uranium dioxide powder, or its lack of plasticity, constitutes a significant shortcoming in compression molding operations and in the porperties of the molded products.
SUMMARY OF THE INVENTION
.. . . _ _ This invention comprises a method of producing coherent compacts from particulate ceramic material wherein the ceramic material is rendered more plastic, or less brittle, while undergoing compression molding by providing a novel binder system including a multifunctional primary amine with carbon dioxide gas. Thus the invention entails a process comprising a combination of operations acting upon the specified ingredients, including the essential provision of carbon dio~ide gas for the amine compound contained in the particulate ceramic nuclear fuel material.
OBJECTS OF T~E IN~E~TION
.
It is a primary object of this invention to provide an improved method for rendering particulate ceramic material more amenable to compression molding.
It is another object of this invention to provide means for overcoming the brittle nature of ceramic particles and to impart plasticity to such a material whereby it can be compression molded under essentially all compacting conditions and at high rates with a lower level of rejects.
~ further object of this invention is to provide a method for improving the compression molding of particulate ceramic materials comprising uranium dioxide po~der into ; 35 coherent compacts and increasing the resistance of such compacts of ceramic materials to fracture and fissure
3~
24-~F-04540 propagation during compression molding and thereafter, including the sintered products of the molded material.
A still further object of this invention is to provide a method of producing nuclear fuel pellets comprising uranium dioxide from particulate cexamic material wherein the particulate ceramic is compression molded -to a coherent compact at fast rates with minimal rejects due to fractures in either the unfired coherent compact or in its sintered product.
D~SCRIPTION OF THE D~AWING
The drawing comprises a flow sheet diagram illustrating the steps of the method of this invention.
DETAILED DESCRIPTION OF THE IN~ENTION
This invention comprises an improved method for producing a fissiona~le nuclear fuel product in pellet form from particulate ceramic ma-terial utilizing a fugitive binder which is subsequently removed during -the sintering operation. The method includes the process of compression molding of particulate ceramic material comprising uranium dioxide powder combined with a fugitive binder comprising a multifunctional primar~ amine with carbon dioxide gas to form coherent compacts of apt dimensions, and there-after sintering the compacts to produce integrated bodies of ~issionable nuclear fuel suitable for use in nuclear reactors.
The particulate fissionable nuclear fuel materials for use in this invention comprise various materials used as nuclear fuels for nuclear reactors, including ceramic compounds such as oxides of uranium, plutonium and thorium.
Preferred fuel compounds consist of uranium oxide, plutonium oxide, thorium oxide, and mixtures thereof.
The particulate nuclear fue] material in the practice of the invention can also include various additives such as neutron absorbing materials comprsing gadolinium to moderate neutron flux densitiesO
Fugitive binders suitable for use in the practice of ~2ql'~3~

this invention comprise the amines disclosed and claimed in the above identified applications for patent Serial Nos.
416,427 and 404i023. These include multifunctional primary amines selected from the group consisting of ethylene diamine; 3.3 diaminodipropylamine; 1.3 diaminopropane; 1.6 diaminohexane; 1.7 diaminoheptane; diethylenetriamine; and 3-dimethylaminopropylamine. Such hinder agent are preferable employed in amounts of from about 0.3% to about 4% by weight of the amine compound based upon the weight of the nuclear fuel material. Amounts of amine beyond about
4% do not generally provide a proportionally commenserate benefit in bonding capacity, and may introduce unwanted effects which can compromise any advantages or the cos-ts of including greater amounts of the bonding agent.
In accordance with the method of this invention, the amine is added to the particulate ceramic fuel material containing uranium dioxide and the binder blended substantially uniformly through the particulate material.
Then carbon dioxide gas is passed through the prepared blend of particulate material containing the amine in an amount of gas of at least a~out one mole of carbon dioxide gas for each gram mole of NH2 in the amine. Thereafter, the blend of particulate ceramic material and added amine-containing ~inder with the carbon dioxide gas is compressed into a coherent compact of suitable dimensions in accordance with procedures and means of the art. The method of this invention enables the effective use of such blends in high speed, continuous production rotary press devices and operations.
The "green" (unfired~ coherent compacts thus formed are then sintered in accordance with the practices and procedures of the art to expel binder material and integrate the ceramic particles into a uniform and continuous body.
The sintered product~ t~pically in the form of a pellet, is thereafter yround to specified dimensions for its designated services.

~L%'~03'~

Blending of the added amine can be effected with any appropriate "dry" mixing apparatus including low shear blenders such as fluidized bed, slab and ribbon blenders, and high shear or intensive blenders such as vibratory mills, ball mills and centrifugal mills.
The blending of the particulate material with the amine, and thereafter the introduction of the carbon dioxide gas, should include a dwell time of at least about 20 minutes and preferahly at least about 40 minutes.
This dwell period prov;des for the amine-containing binder with the gas to react directly with the uranium dioxide producing an effective bonding mechanism, and also the modification of the brittle mixture of ceramic particles to render them more plastic and amenable in compression molding.
Upon applying the amine and carbon dioxide gas of this invention to the particulate ceramic material, the blend thereof can be compression molded into coherent compacts or handleable pellets by substantially any effective means or device in accordance with the technology of this field such as is described in the prior art/ including the above cited patents and pending applications.
The coherent compacts or pellets of the compression mo]ded, binder containing particulate ceramic material ~S are then sintered to expel binder material therefrom and integrate the ceramic particles into an essentially continuous body or mass of substantially uniform consistency, and relatively high strength and good resistance to fracture.
~atex or other suitable solvent may be added to the amine prior to its addition to the particulate ceramic fuel material containing uranium dioxide to reduce the corrosive ef~ect of the amine upon certain materials such as rubber lining which may be present ;n processing equipment.
~hen water is included, its content in the blend must be adjusted to a final ~mount of below about 5000 parts per million by weight.

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3~

_ g _ Examples of preferred procedures for the practice of the method of this invention are as follows.
Example I . Ten ~ilograms of UO2powder and a solution of 1 1/2% ethylene diamine in 0.4% water, both on a UO2 weight basis, were blended for 20 minutes in a 1 cubic foot Sweco vibratory mill containing 3/4" aluminum cylinder~ as media. Carbon dioxide gas was then introduced into the mill at a rate of 1 cubic foot per minute while the mill operated for an additional 30 minutes. (H2O added to reduce corresive attac]~ on particular material used to line vibratory is not necessary for all materials.) The foregoing procedure was then repeated except 1 cubic foot of nitrogen gas was substituted in place of the carbon dioxide gas.
Compacts were then die pressed ~rom the source UO2 powder (not treatment), the carbon dioxide treated, and the nitrogen treated UO2 powder. These compacts were then tested in diametral compression which allows a measure of tensile strength (TS~, total elongation ETotal plastic elonglation Ep, and F which is a measure of crack blunting after ~ailure has occurred.

TS ETotal P F3 Source UO2 powder 22psi 22y 4 o UO2+H ethylene diamine 52 68 39 3~5 U2 ~ ethylene diamine 20 39 18 0.5 + H20 + N2 The UO2 ethylene diamine, and CO2 obviously functions well as a binder by increasing tensile strength, total elongat~on, plastic elongation, ana elongation after failure.

`` ~2~ 37~

Example 2. Twenty-one kilograms of UO2 powder and a solution of 0.6% of ethylene diamine in 0.8% water, both on a UO2 weight ~asis, well blended in a 3 cubic foot Sweco vibratory mill containing 3/4" aluminum cylinders. ~H2O added to reduce corrosive attack on vibratory mill lining.) 0.7~ ammonium oxalate was also added as a pore former for creating voids in the sintered pellets which will be fabricated from the powder. The mill operated 5 minutes to blen~ the ethylene diamine in water solution and ammonium oxalate. Carbon dioxide gas was then introduced into the mill at 6 cubic feet per minute with the mill running. The carbon dioxide gas treatment was then followed by 20 minutes of mill operation wi-th 20 cubic feet of nitrogen flowing which by previous testing should evaporate the final water content to less than 5000 ppm. Diametral tests on compacts made from the powder revealed less than desired plasticity. The powder which was still in the mill was given an additional 6 cfm carbon dioxide ~low for 10 minutes with the mill running. Diametral compression testing yielding the following properties:
Tensile Strength 67psi Total Elongation 77 Plastic ElongatIon 43 F3 20~

The source tno additi~e~ UO2 diametral compression test results from exclmple 1 may be used for comparison in establishing the performance of this binder.
Example_3. Two hundred fifty grams of uranium dioxide along with two hundred grams of 1/2" aluminum grinding media were introduced into an 8 ounce polyethylene bottle. 2.5~ ethylene diamine was then added (6. 25 grams) and the bottle placed on a paint shaker for 15 minutes.
The aluminum balls were then screened from the blended po~der which was next placed in a 6" fritted glass porous 3L~ 3~9~

funnel. 400 cfh of carbon dioxide gas was then flowed upward through the powder creating the binder. Diametral compression at various time intervals of carbon dioxide treatment are as follows:

Tensile To-tal Plastic F
Strength Elongation Elongation 15 min CO2 106 psi 1151~ 70~ 48 30 min CO2 154 psi 144~ -- 21 45 min CO2 177 psi 166~ -- 16 60 min CO2 240 psi 106~ 46" 3~J

No water used in this example

Claims (13)

The embodiments of the invention in which an exclusive property or privilege is claimed are defined as follows:
1. A method of producing coherent compacts of particulate ceramic nuclear fuel material whereby the ceramic material is rendered more plastic and amenable to processing, consisting essentially of the sequence of steps of:
a) adding a fugitive binder consisting essentially of at least one amine selected from the group consisting of ethylene diamine, 3.3 diaminodipropylamine, 1.3 diamino-propane, 1.6 diaminohexane, 1.7 diaminoheptane, diethylene-triamine, and 3-dimethylaminopropylamine to particulate nuclear fuel material of uranium dioxide and blending the binder therethrough;
b) thereafter introducing carbon dioxide gas into the blend of particular fuel material and amine binder;
and c) pressing the resultant blend comprising particulate fuel material and amine binder having had the carbon dioxide gas introduced therein into a coherent compact.
2. The method of claim 1, wherein the fugitive binder is a water solution of the amine.
3. The method of claim 1, wherein the fugitive binder comprises a multifunctional primary amine.
4. The method of claim 1, wherein the fugitive binder comprises ethylene diamine.
5. A method of producing coherent compacts of particulate ceramic nuclear fuel material whereby the ceramic material is rendered more plastic and amenable to processing, consisting essentially of the sequence of steps of:
a) adding a fugitive binder consisting essentially of at least one multifunctional primary amine selected from the group consisting of ethylene diamine, 3.3 diaminodipropylamine, 1.3 diaminopropane, 1.6 diaminohexane, 1.7 diaminoheptane, diethylenetriamine, and 3-dimethylaminopropylamine to particulate nuclear fuel material consisting of uranium dioxide and blending the binder therethrough;
b) thereafter introducing carbon dioxide gas into the blend of particulate fuel material and amine binder;
and c) pressing the resultant blend comprising particulate fuel material and amine binder having had the carbon dioxide gas introduced therein into a coherent compact.
6. The method of claim 5, wherein the fugitive binder is a water solution of the multifunctional primary amine.
7. The method of claim 5, wherein the fugitive binder comprises ethylene diamine.
8. The method of claim 5 wherein multifunctional primary amine is added to the particulare nuclear fuel material in amount of about 0.3 to about 4% by weight of the amine based upon the weight of the fuel material.
9. A method of producing coherent compacts of particulate ceramic nuclear fuel material whereby the ceramic material is rendered more plastic and amenable to processing r consisting essentially of the sequence of steps of:
a) adding a fugitive binder consisting essentially of ethylene diamine to particulate nuclear fuel material consisting of uranium dioxide and blending the binder therethrough;
b) thereafter introducing carbon dioxide gas into the blend comprising particulate fuel material and amine binder;
c) pressing the resultant blend comprising particulate nuclear fuel material and ethylene diamine having had the carbon dioxide gas introduced therein into a coherent compact; and d) sintering the compact of the blend to expel binder material and integrate the particulate nuclear fuel material into a uniform body.
10. The method of claim 9, wherein the fugitive binder is a water solution of the multifunctional primary amine.
11. The method of claim 9, wherein the carbon dioxide gas is introduced in amount of at elast one mole of carbon dioxide gas for each gram mole NH2 in the amine.
12. The method of claim 9, wherein multifunctional primary amine is added to the particulate nuclear fuel material in amount of about 0.3 to about 4% by weight of the amine based upon the weight of the fuel material.
13. A method of producing coherent compacts of particulate ceramic nuclear fuel material whereby the ceramic material is rendered more plastic and amenable to processing, consisting essentially of the sequence of steps of:
a) adding a fugitive binder consisting essentially of at least one amine selected from the group consisting of ethylene diamine, 3.3 diaminodipropylamine, 1.3 diaminopropane, 1.6 diaminohexane, diethylene triamine and 3-dimethylaminopropylamine to particulate nuclear fuel material consisting of uranium dioxide in amount of about 0.5 to about 4% by weight of the amine based upon the weight of the fuel material and blending the binder thereof;
b) thereafter introducing carbon dioxide gas into the blend comprising particulate fuel material and amine binder in amount of at least one mole of carbon dioxide gas for each gram mole of NH2 in the amine;
c) pressing the resultant blend comprising particulate nuclear fuel material and ethylene diamine having had the carbon dioxide gas introduced therein into a coherent compact; and
Claim 13 continued:
d) sintering the compact of the blend to expel binder material and integrate the particulate nuclear fuel material into a uniform body.
CA000436352A 1983-09-09 1983-09-09 Method for the manufacture of nuclear fuel products Expired CA1200374A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CA000436352A CA1200374A (en) 1983-09-09 1983-09-09 Method for the manufacture of nuclear fuel products

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CA000436352A CA1200374A (en) 1983-09-09 1983-09-09 Method for the manufacture of nuclear fuel products

Publications (1)

Publication Number Publication Date
CA1200374A true CA1200374A (en) 1986-02-11

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Family Applications (1)

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CA000436352A Expired CA1200374A (en) 1983-09-09 1983-09-09 Method for the manufacture of nuclear fuel products

Country Status (1)

Country Link
CA (1) CA1200374A (en)

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