CA1068832A - Target for production of molybdenum-99 - Google Patents
Target for production of molybdenum-99Info
- Publication number
- CA1068832A CA1068832A CA255,556A CA255556A CA1068832A CA 1068832 A CA1068832 A CA 1068832A CA 255556 A CA255556 A CA 255556A CA 1068832 A CA1068832 A CA 1068832A
- Authority
- CA
- Canada
- Prior art keywords
- fuel
- target
- reactor
- gap
- spacing
- 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
- ZOKXTWBITQBERF-AKLPVKDBSA-N Molybdenum Mo-99 Chemical compound [99Mo] ZOKXTWBITQBERF-AKLPVKDBSA-N 0.000 title claims abstract description 10
- 229950009740 molybdenum mo-99 Drugs 0.000 title claims abstract description 7
- 238000004519 manufacturing process Methods 0.000 title description 3
- 239000000446 fuel Substances 0.000 claims abstract description 15
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 claims abstract description 12
- 229910052770 Uranium Inorganic materials 0.000 claims abstract description 11
- 229910001093 Zr alloy Inorganic materials 0.000 claims abstract description 7
- 239000003758 nuclear fuel Substances 0.000 claims abstract description 6
- 229910052751 metal Inorganic materials 0.000 claims description 9
- 239000002184 metal Substances 0.000 claims description 9
- 230000004907 flux Effects 0.000 claims description 4
- 229910001220 stainless steel Inorganic materials 0.000 claims description 4
- 239000010935 stainless steel Substances 0.000 claims description 4
- 239000011888 foil Substances 0.000 abstract description 9
- 239000000843 powder Substances 0.000 abstract description 4
- 239000002826 coolant Substances 0.000 description 4
- 125000006850 spacer group Chemical group 0.000 description 4
- 229910052782 aluminium Inorganic materials 0.000 description 2
- XAGFODPZIPBFFR-UHFFFAOYSA-N aluminium Chemical compound [Al] XAGFODPZIPBFFR-UHFFFAOYSA-N 0.000 description 2
- 238000000034 method Methods 0.000 description 2
- 229940121896 radiopharmaceutical Drugs 0.000 description 2
- 239000012217 radiopharmaceutical Substances 0.000 description 2
- 230000002799 radiopharmaceutical effect Effects 0.000 description 2
- JFALSRSLKYAFGM-OIOBTWANSA-N uranium-235 Chemical compound [235U] JFALSRSLKYAFGM-OIOBTWANSA-N 0.000 description 2
- 206010028980 Neoplasm Diseases 0.000 description 1
- 229910000711 U alloy Inorganic materials 0.000 description 1
- QCWXUUIWCKQGHC-UHFFFAOYSA-N Zirconium Chemical compound [Zr] QCWXUUIWCKQGHC-UHFFFAOYSA-N 0.000 description 1
- 229910045601 alloy Inorganic materials 0.000 description 1
- 239000000956 alloy Substances 0.000 description 1
- QVGXLLKOCUKJST-UHFFFAOYSA-N atomic oxygen Chemical compound [O] QVGXLLKOCUKJST-UHFFFAOYSA-N 0.000 description 1
- 238000001514 detection method Methods 0.000 description 1
- 238000002405 diagnostic procedure Methods 0.000 description 1
- 230000004992 fission Effects 0.000 description 1
- 230000003902 lesion Effects 0.000 description 1
- 239000007788 liquid Substances 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 229910052760 oxygen Inorganic materials 0.000 description 1
- 239000001301 oxygen Substances 0.000 description 1
- 239000008188 pellet Substances 0.000 description 1
- 239000002901 radioactive waste Substances 0.000 description 1
- 238000011084 recovery Methods 0.000 description 1
- 229910052726 zirconium Inorganic materials 0.000 description 1
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
- G21C3/04—Constructional details
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21G—CONVERSION OF CHEMICAL ELEMENTS; RADIOACTIVE SOURCES
- G21G1/00—Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation or particle bombardment, e.g. producing radioactive isotopes
- G21G1/04—Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation or particle bombardment, e.g. producing radioactive isotopes outside nuclear reactors or particle accelerators
- G21G1/06—Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation or particle bombardment, e.g. producing radioactive isotopes outside nuclear reactors or particle accelerators by neutron irradiation
- G21G1/08—Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation or particle bombardment, e.g. producing radioactive isotopes outside nuclear reactors or particle accelerators by neutron irradiation accompanied by nuclear fission
-
- 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
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Chemical & Material Sciences (AREA)
- Chemical Kinetics & Catalysis (AREA)
- General Chemical & Material Sciences (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Particle Accelerators (AREA)
Abstract
TITLE
INVENTOR
MELVILLE A. FERADAY
ABSTRACT OF THE DISCLOSURE
A nuclear fuel structure for use as a fuel for a small nuclear reactor or as a target to produce Molybdenum -99 that is formed from two annular spaced zirconium alloy tubes defining a thin but constant annular gap between with the gap being filled with enriched uranium in the form of a foil or a compacted powder. In the preferred version, the spacing is achieved by a spacing means in the form of a wire or ridge extending between tubes.
INVENTOR
MELVILLE A. FERADAY
ABSTRACT OF THE DISCLOSURE
A nuclear fuel structure for use as a fuel for a small nuclear reactor or as a target to produce Molybdenum -99 that is formed from two annular spaced zirconium alloy tubes defining a thin but constant annular gap between with the gap being filled with enriched uranium in the form of a foil or a compacted powder. In the preferred version, the spacing is achieved by a spacing means in the form of a wire or ridge extending between tubes.
Description
` 1068832 This invention relates to a nuclear fuel structure for use in a nuclear reactor or other region of neutron flux as a fuel or as target to produce Molybdenum-99.
Molybdenum-99 is produced as fission product from the irradiation of Uranium-235 or other ~k}u*~ material and is then supplied to the radio-pharmaceutical industry to make Technitium-99 generators. Tc-9~ is the radionuclide "daughter"
of Mo-99 and is used in hospitals for a broad range of diagnostic procedures in nuclear medecine particularly in the field of 1~ tumor or lesion detection. Its properties have made Tc-99 one of the most widely used diagnostic tools in the medical field and the usè of this radio-isotope is expected to soon equal and exceed the total use of all other isotopes currently used by the radio-pharmaceutical industry. The target used at the present time is a rod of Aluminum-21 wt. % Uranium ex-trusion clad in a finned aluminum sheath. This target is inefficient in producing Mo-99 in that the recovery rate is less than 40~ and large quantities or radioactive wastes, mainly aluminum solutions are produced.
~here is also at the present time, a requirement for small, safe, but generally simple nuclear reactors for use as ~`~
neutron generators and as sources of small amounts of power. An ; example of such a reactor is the Atomic Energy of Canada Limited/
University of Toronto "S~OWPOKE" reactor. This reactor at present uses fuel elements in the form of cylindrical metal containe~s filled with enriched uranium alloy positioned in a ; moderator/coolant liquid. It would be highly desirable to have fuel elements with improved heat transfer, lower neutron self-shieldins, and higher burnup.
It is an object of the present invention to provide a nuclear fuel structure useful as a fuel for small reactors and as a neutron target for Molybdenum-99 production '. . . ` , ` . .- . :
that is more efficient and cheaper to process than present devices.
This and other objects of the invention are achieved by a nuclear fuel structure that is formed from two annular spaced zirconium alloy tubes defining a thin but constant annular gap between with the gap being filled with enriched uranium in the form of a foil or a compacted powder.
In the preferred version, the spacing is achieved by a spacing means in the form of a wire or ridge extending between tubes.
In drawings, which illustrate embodiments ; of the invention,.
.- Figure 1 is a cross-section of one version of the target structure~..
Figure 2 is a cross-section of a second version of the target~structure, -j~ Figure 3 shows a variant spacing means, :
`~ and Figure 4 shows the target in the reactor .
tube. .
~eferring to figure 1, the target 10 is .::
. made up of a thin uranium (UO2) tubular foil 11 encased between two sheaths 12a and 12b made of zirconium alloy, stainless steel, or other suitable metal. A twist foil 13 of zirconium .
alloy, stainless steel or other suitable metal may be ; attached i~ the central region as shown to provide improved heat trans~er between coolant 14 that in operation passes through the central region and the target structure. Coolant also passes in the outer region 15 between the target structure and the reactor tube (not shown). The UO2 used is highly enriched and normally is in the 90% plus wt.% U-235 in relation to U-238.
This version of the target is made as follows . . . .
~ 1~68832 using 0.051 mm thick uranium (93wt~) foil and two zirconium alloy sheaths having a clearance of about 0.1 to 0.2 mm as required for assembly:
1) assemble the uranium foil between the two sheaths. 2) weld shut one end of the zirconium alloy annulus 3) if necessary swage or planetary roll the outside sheath to reduce its diameter and the clearance between the two sheaths so as to leave about 0.1 mm clearance in addition to the thickness of the uranium foil. 4) heat the uranium metal in steam, air, or oxygen to oxidize the metal. The volume increase of the fuel as it oxidizes will fill any residual radial clearance and slightly increase the diameter of the sheath. 5) weld seal the top end of the element.
This version is a satisfactory design but its use might be limited as it may be difficult to get 0.05 mm uranium foil.
Referring to figure 2 a preferred version is shown with the two sheaths 12a and 12b being separated by three or more (4 shown) spacer wires 16 spot welded to the outer surface of the inner sheath tube 12a. The central annular region 17 is filled with a powder made from crushed UO2 -pellets or by other suitable means. The target is made by loading the fine UO2 powder (e.g. -~00 mesh) into the annulus between sheaths with the spacer wires maintaining the very ~ small gap spacing (as thin as 0.13 mm and vibratorily compacting - to a tap density of about 70% TD (theoretical density). The ends of the structure (typically about 150mm long) are then weld sealed. The spacing between sheaths is reduced by ~-hydrostatic or mechanical forming to increasing the fuel density to about 85% TD.
Figure 3 shows a~ alternative spacing means for maintaining the required fine gap spacing between sheaths.
' .: , ' ,:
- 3 - ~
In this case the inner sheath 12a is formed with longitudinal ridges 24 extending over at least same portion of the length of the tube to provide the spacing between sheaths 12a and 12b. This spacing can also be achieved by having the ridges formed inwardly in the outer tube 12b. The spacers may also be warts or protuberances of the appropriate height formed on the surface.
In operation, the tàrget structure 10 would preferabl~ be loaded on a central rod 19 and held in position by spacers 20 and then inserted in the reactor tube 21 for entry into the neutron flux region of the reactor core.
Coolant passes through annular regions 22 and 23.
Figure 4 shows the targèt in position in the reactor.
` The above design of target has been found ` to be`more efficient in Mo-99 production than existing types.
` After irradiation in the reactor, the target fuel is processed ` to produce Tc-99 but there are existing techniques for this and therefore this is not a concern of the present invention.
In addition this type of fuel structure has been ound to have important advantages for use as a fuel for small reactors. Because the fuel foil or layer is thin, a high area to volume ratio is achieved and this is important for efficient heat transfer, low neutron self-shielding, and high burn-up. `
.
.
,., j .
, ,, ; .
' ;~
- 4 - ^
.
Molybdenum-99 is produced as fission product from the irradiation of Uranium-235 or other ~k}u*~ material and is then supplied to the radio-pharmaceutical industry to make Technitium-99 generators. Tc-9~ is the radionuclide "daughter"
of Mo-99 and is used in hospitals for a broad range of diagnostic procedures in nuclear medecine particularly in the field of 1~ tumor or lesion detection. Its properties have made Tc-99 one of the most widely used diagnostic tools in the medical field and the usè of this radio-isotope is expected to soon equal and exceed the total use of all other isotopes currently used by the radio-pharmaceutical industry. The target used at the present time is a rod of Aluminum-21 wt. % Uranium ex-trusion clad in a finned aluminum sheath. This target is inefficient in producing Mo-99 in that the recovery rate is less than 40~ and large quantities or radioactive wastes, mainly aluminum solutions are produced.
~here is also at the present time, a requirement for small, safe, but generally simple nuclear reactors for use as ~`~
neutron generators and as sources of small amounts of power. An ; example of such a reactor is the Atomic Energy of Canada Limited/
University of Toronto "S~OWPOKE" reactor. This reactor at present uses fuel elements in the form of cylindrical metal containe~s filled with enriched uranium alloy positioned in a ; moderator/coolant liquid. It would be highly desirable to have fuel elements with improved heat transfer, lower neutron self-shieldins, and higher burnup.
It is an object of the present invention to provide a nuclear fuel structure useful as a fuel for small reactors and as a neutron target for Molybdenum-99 production '. . . ` , ` . .- . :
that is more efficient and cheaper to process than present devices.
This and other objects of the invention are achieved by a nuclear fuel structure that is formed from two annular spaced zirconium alloy tubes defining a thin but constant annular gap between with the gap being filled with enriched uranium in the form of a foil or a compacted powder.
In the preferred version, the spacing is achieved by a spacing means in the form of a wire or ridge extending between tubes.
In drawings, which illustrate embodiments ; of the invention,.
.- Figure 1 is a cross-section of one version of the target structure~..
Figure 2 is a cross-section of a second version of the target~structure, -j~ Figure 3 shows a variant spacing means, :
`~ and Figure 4 shows the target in the reactor .
tube. .
~eferring to figure 1, the target 10 is .::
. made up of a thin uranium (UO2) tubular foil 11 encased between two sheaths 12a and 12b made of zirconium alloy, stainless steel, or other suitable metal. A twist foil 13 of zirconium .
alloy, stainless steel or other suitable metal may be ; attached i~ the central region as shown to provide improved heat trans~er between coolant 14 that in operation passes through the central region and the target structure. Coolant also passes in the outer region 15 between the target structure and the reactor tube (not shown). The UO2 used is highly enriched and normally is in the 90% plus wt.% U-235 in relation to U-238.
This version of the target is made as follows . . . .
~ 1~68832 using 0.051 mm thick uranium (93wt~) foil and two zirconium alloy sheaths having a clearance of about 0.1 to 0.2 mm as required for assembly:
1) assemble the uranium foil between the two sheaths. 2) weld shut one end of the zirconium alloy annulus 3) if necessary swage or planetary roll the outside sheath to reduce its diameter and the clearance between the two sheaths so as to leave about 0.1 mm clearance in addition to the thickness of the uranium foil. 4) heat the uranium metal in steam, air, or oxygen to oxidize the metal. The volume increase of the fuel as it oxidizes will fill any residual radial clearance and slightly increase the diameter of the sheath. 5) weld seal the top end of the element.
This version is a satisfactory design but its use might be limited as it may be difficult to get 0.05 mm uranium foil.
Referring to figure 2 a preferred version is shown with the two sheaths 12a and 12b being separated by three or more (4 shown) spacer wires 16 spot welded to the outer surface of the inner sheath tube 12a. The central annular region 17 is filled with a powder made from crushed UO2 -pellets or by other suitable means. The target is made by loading the fine UO2 powder (e.g. -~00 mesh) into the annulus between sheaths with the spacer wires maintaining the very ~ small gap spacing (as thin as 0.13 mm and vibratorily compacting - to a tap density of about 70% TD (theoretical density). The ends of the structure (typically about 150mm long) are then weld sealed. The spacing between sheaths is reduced by ~-hydrostatic or mechanical forming to increasing the fuel density to about 85% TD.
Figure 3 shows a~ alternative spacing means for maintaining the required fine gap spacing between sheaths.
' .: , ' ,:
- 3 - ~
In this case the inner sheath 12a is formed with longitudinal ridges 24 extending over at least same portion of the length of the tube to provide the spacing between sheaths 12a and 12b. This spacing can also be achieved by having the ridges formed inwardly in the outer tube 12b. The spacers may also be warts or protuberances of the appropriate height formed on the surface.
In operation, the tàrget structure 10 would preferabl~ be loaded on a central rod 19 and held in position by spacers 20 and then inserted in the reactor tube 21 for entry into the neutron flux region of the reactor core.
Coolant passes through annular regions 22 and 23.
Figure 4 shows the targèt in position in the reactor.
` The above design of target has been found ` to be`more efficient in Mo-99 production than existing types.
` After irradiation in the reactor, the target fuel is processed ` to produce Tc-99 but there are existing techniques for this and therefore this is not a concern of the present invention.
In addition this type of fuel structure has been ound to have important advantages for use as a fuel for small reactors. Because the fuel foil or layer is thin, a high area to volume ratio is achieved and this is important for efficient heat transfer, low neutron self-shielding, and high burn-up. `
.
.
,., j .
, ,, ; .
' ;~
- 4 - ^
.
Claims (2)
1. A nuclear fuel structure for use in a reactor or other neutron flux field as a fuel or to produce molybdenum-99 by irradiation, comprising inner and outer spaced metal tubes defining a thin but constant annular gap between, and structural means comprising three or more wires attached along some portion of the length of the outer surface of the inner tube or the inner surface of the outer tube for maintaining said annular gap spacing, said gap being filled with enriched uranium fuel and said tubes being made of a metal of the group zirconium alloy, stainless steel.
2. A nuclear fuel structure for use in a reactor or other neutron flux field as a fuel or to produce molybdenum-99 by irradiation, comprising inner and outer spaced metal tubes defining a thin but constant annular gap between, and structural means comprising three or more ridges or protuberances formed along some portion of the length of the outer surface of the inner tube or the inner surface of the outer tube for maintaining said annular gap spacing, said gap being filled with enriched uranium fuel and said tubes being made of a metal of the group zirconium alloy, stainless steel.
Priority Applications (2)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CA255,556A CA1068832A (en) | 1976-06-23 | 1976-06-23 | Target for production of molybdenum-99 |
| FR7710088A FR2356243A1 (en) | 1976-06-23 | 1977-04-04 | Nuclear fuel structure for molybdenum 99 prodn. - comprising concentric metal tubes with uranium fuel in annular space |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CA255,556A CA1068832A (en) | 1976-06-23 | 1976-06-23 | Target for production of molybdenum-99 |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CA1068832A true CA1068832A (en) | 1979-12-25 |
Family
ID=4106276
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CA255,556A Expired CA1068832A (en) | 1976-06-23 | 1976-06-23 | Target for production of molybdenum-99 |
Country Status (2)
| Country | Link |
|---|---|
| CA (1) | CA1068832A (en) |
| FR (1) | FR2356243A1 (en) |
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US5615238A (en) * | 1993-10-01 | 1997-03-25 | The United States Of America As Represented By The United States Department Of Energy | Method for fabricating 99 Mo production targets using low enriched uranium, 99 Mo production targets comprising low enriched uranium |
| RU2476941C2 (en) * | 2010-11-01 | 2013-02-27 | Закрытое акционерное общество научно-производственное объединение "Уральская химико-технологическая компания Урал-ХТК" | TARGET FOR PRODUCING 99Mo ISOTOPE |
| RU2511215C1 (en) * | 2012-10-02 | 2014-04-10 | Открытое акционерное общество "Государственный научный центр Научно-исследовательский институт атомных реакторов" | Target for producing mo-99 isotope |
| WO2022167008A1 (en) * | 2021-02-02 | 2022-08-11 | 上海核工程研究设计院有限公司 | Irradiation target containing support rod for producing mo-99 isotope in heavy water reactor |
Families Citing this family (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| FR2513797A1 (en) * | 1981-09-30 | 1983-04-01 | Commissariat Energie Atomique | HIGHER NEUTRON PROTECTION DEVICE FOR NUCLEAR REACTOR ASSEMBLY |
| FR2781079B1 (en) * | 1998-07-09 | 2000-09-15 | Cerca Compagnie Pour L Etude E | PRIMARY TARGET FOR THE FORMATION OF FISSION PRODUCTS |
| CN103038831A (en) * | 2010-07-29 | 2013-04-10 | 由俄勒冈州高等教育管理委员会代表的俄勒冈州立大学 | Isotope production target |
-
1976
- 1976-06-23 CA CA255,556A patent/CA1068832A/en not_active Expired
-
1977
- 1977-04-04 FR FR7710088A patent/FR2356243A1/en active Granted
Cited By (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US5615238A (en) * | 1993-10-01 | 1997-03-25 | The United States Of America As Represented By The United States Department Of Energy | Method for fabricating 99 Mo production targets using low enriched uranium, 99 Mo production targets comprising low enriched uranium |
| US6160862A (en) * | 1993-10-01 | 2000-12-12 | The United States Of America As Represented By The United States Department Of Energy | Method for fabricating 99 Mo production targets using low enriched uranium, 99 Mo production targets comprising low enriched uranium |
| RU2476941C2 (en) * | 2010-11-01 | 2013-02-27 | Закрытое акционерное общество научно-производственное объединение "Уральская химико-технологическая компания Урал-ХТК" | TARGET FOR PRODUCING 99Mo ISOTOPE |
| RU2511215C1 (en) * | 2012-10-02 | 2014-04-10 | Открытое акционерное общество "Государственный научный центр Научно-исследовательский институт атомных реакторов" | Target for producing mo-99 isotope |
| WO2022167008A1 (en) * | 2021-02-02 | 2022-08-11 | 上海核工程研究设计院有限公司 | Irradiation target containing support rod for producing mo-99 isotope in heavy water reactor |
Also Published As
| Publication number | Publication date |
|---|---|
| FR2356243B1 (en) | 1980-04-18 |
| FR2356243A1 (en) | 1978-01-20 |
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