CA1107054A - Process for the production of ceramic plutonium uranium nuclear fuel in the form of sintered pellets - Google Patents
Process for the production of ceramic plutonium uranium nuclear fuel in the form of sintered pelletsInfo
- Publication number
- CA1107054A CA1107054A CA299,340A CA299340A CA1107054A CA 1107054 A CA1107054 A CA 1107054A CA 299340 A CA299340 A CA 299340A CA 1107054 A CA1107054 A CA 1107054A
- Authority
- CA
- Canada
- Prior art keywords
- plutonium
- uranium
- microspheres
- oxide
- xerogel
- 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
- WJWSFWHDKPKKES-UHFFFAOYSA-N plutonium uranium Chemical compound [U].[Pu] WJWSFWHDKPKKES-UHFFFAOYSA-N 0.000 title claims abstract description 52
- 239000000919 ceramic Substances 0.000 title claims abstract description 26
- 239000008188 pellet Substances 0.000 title claims description 92
- 238000000034 method Methods 0.000 title claims description 64
- 238000004519 manufacturing process Methods 0.000 title claims description 34
- 239000003758 nuclear fuel Substances 0.000 title description 8
- 239000004005 microsphere Substances 0.000 claims abstract description 109
- 238000005245 sintering Methods 0.000 claims abstract description 28
- 239000006104 solid solution Substances 0.000 claims abstract description 26
- 239000000446 fuel Substances 0.000 claims abstract description 24
- 150000003671 uranium compounds Chemical class 0.000 claims abstract description 12
- 150000003061 plutonium compounds Chemical class 0.000 claims abstract description 7
- 229910052778 Plutonium Inorganic materials 0.000 claims description 96
- OYEHPCDNVJXUIW-UHFFFAOYSA-N plutonium atom Chemical compound [Pu] OYEHPCDNVJXUIW-UHFFFAOYSA-N 0.000 claims description 94
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 claims description 79
- 229910052770 Uranium Inorganic materials 0.000 claims description 78
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 claims description 43
- 229910052799 carbon Inorganic materials 0.000 claims description 43
- 150000001875 compounds Chemical class 0.000 claims description 42
- 150000004767 nitrides Chemical class 0.000 claims description 31
- 239000000203 mixture Substances 0.000 claims description 25
- 239000000463 material Substances 0.000 claims description 24
- 239000002245 particle Substances 0.000 claims description 20
- XKRFYHLGVUSROY-UHFFFAOYSA-N Argon Chemical compound [Ar] XKRFYHLGVUSROY-UHFFFAOYSA-N 0.000 claims description 18
- 238000006243 chemical reaction Methods 0.000 claims description 17
- 238000002156 mixing Methods 0.000 claims description 16
- 238000007704 wet chemistry method Methods 0.000 claims description 16
- 239000000428 dust Substances 0.000 claims description 14
- 238000010438 heat treatment Methods 0.000 claims description 14
- 238000003825 pressing Methods 0.000 claims description 11
- 238000001879 gelation Methods 0.000 claims description 10
- 229910052786 argon Inorganic materials 0.000 claims description 9
- 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 description 7
- SHZGCJCMOBCMKK-KGJVWPDLSA-N beta-L-fucose Chemical compound C[C@@H]1O[C@H](O)[C@@H](O)[C@H](O)[C@@H]1O SHZGCJCMOBCMKK-KGJVWPDLSA-N 0.000 claims description 7
- 239000007789 gas Substances 0.000 claims description 7
- 229910000439 uranium oxide Inorganic materials 0.000 claims description 7
- UFHFLCQGNIYNRP-UHFFFAOYSA-N Hydrogen Chemical compound [H][H] UFHFLCQGNIYNRP-UHFFFAOYSA-N 0.000 claims description 6
- 238000009826 distribution Methods 0.000 claims description 6
- 239000001257 hydrogen Substances 0.000 claims description 6
- 229910052739 hydrogen Inorganic materials 0.000 claims description 6
- 238000001354 calcination Methods 0.000 claims description 5
- 230000009467 reduction Effects 0.000 claims description 4
- 239000006229 carbon black Substances 0.000 claims description 3
- 238000001556 precipitation Methods 0.000 claims description 2
- 239000007787 solid Substances 0.000 claims 1
- 239000000126 substance Substances 0.000 abstract description 6
- -1 carbides nitrides Chemical class 0.000 abstract description 4
- 229940076400 plutonium Drugs 0.000 description 62
- 239000000843 powder Substances 0.000 description 14
- 238000003980 solgel method Methods 0.000 description 13
- 239000007858 starting material Substances 0.000 description 10
- 239000012527 feed solution Substances 0.000 description 6
- 238000000227 grinding Methods 0.000 description 4
- 238000005453 pelletization Methods 0.000 description 4
- 238000002360 preparation method Methods 0.000 description 4
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 4
- PSPBAKLTRUOTFX-UHFFFAOYSA-N [O-2].[Pu+4].[U+6].[O-2].[O-2].[O-2].[O-2] Chemical compound [O-2].[Pu+4].[U+6].[O-2].[O-2].[O-2].[O-2] PSPBAKLTRUOTFX-UHFFFAOYSA-N 0.000 description 3
- 229910052751 metal Inorganic materials 0.000 description 3
- 239000002184 metal Substances 0.000 description 3
- 238000006722 reduction reaction Methods 0.000 description 3
- 239000000243 solution Substances 0.000 description 3
- 229910052695 Americium Inorganic materials 0.000 description 2
- JWCCDJCEINDHSG-UHFFFAOYSA-N [C].[Pu].[U] Chemical compound [C].[Pu].[U] JWCCDJCEINDHSG-UHFFFAOYSA-N 0.000 description 2
- LXQXZNRPTYVCNG-UHFFFAOYSA-N americium atom Chemical compound [Am] LXQXZNRPTYVCNG-UHFFFAOYSA-N 0.000 description 2
- 238000012824 chemical production Methods 0.000 description 2
- 230000001419 dependent effect Effects 0.000 description 2
- 238000009792 diffusion process Methods 0.000 description 2
- 239000012467 final product Substances 0.000 description 2
- 229910001385 heavy metal Inorganic materials 0.000 description 2
- 239000007788 liquid Substances 0.000 description 2
- 238000012423 maintenance Methods 0.000 description 2
- 150000002739 metals Chemical class 0.000 description 2
- 230000005855 radiation Effects 0.000 description 2
- 230000002269 spontaneous effect Effects 0.000 description 2
- 239000000725 suspension Substances 0.000 description 2
- ZSLUVFAKFWKJRC-IGMARMGPSA-N 232Th Chemical compound [232Th] ZSLUVFAKFWKJRC-IGMARMGPSA-N 0.000 description 1
- 241000518994 Conta Species 0.000 description 1
- DGAQECJNVWCQMB-PUAWFVPOSA-M Ilexoside XXIX Chemical compound C[C@@H]1CC[C@@]2(CC[C@@]3(C(=CC[C@H]4[C@]3(CC[C@@H]5[C@@]4(CC[C@@H](C5(C)C)OS(=O)(=O)[O-])C)C)[C@@H]2[C@]1(C)O)C)C(=O)O[C@H]6[C@@H]([C@H]([C@@H]([C@H](O6)CO)O)O)O.[Na+] DGAQECJNVWCQMB-PUAWFVPOSA-M 0.000 description 1
- 241000643898 Plutonium Species 0.000 description 1
- 229910052776 Thorium Inorganic materials 0.000 description 1
- 230000003466 anti-cipated effect Effects 0.000 description 1
- 239000007864 aqueous solution Substances 0.000 description 1
- 238000009835 boiling Methods 0.000 description 1
- 229910010293 ceramic material Inorganic materials 0.000 description 1
- 239000007795 chemical reaction product Substances 0.000 description 1
- 238000001035 drying Methods 0.000 description 1
- 230000004992 fission Effects 0.000 description 1
- 230000009969 flowable effect Effects 0.000 description 1
- 230000037406 food intake Effects 0.000 description 1
- 238000000265 homogenisation Methods 0.000 description 1
- 238000011835 investigation Methods 0.000 description 1
- 239000011159 matrix material Substances 0.000 description 1
- 150000001247 metal acetylides Chemical class 0.000 description 1
- OYEHPCDNVJXUIW-QQVBLGSISA-N plutonium-236 Chemical compound [236Pu] OYEHPCDNVJXUIW-QQVBLGSISA-N 0.000 description 1
- 230000001681 protective effect Effects 0.000 description 1
- 238000011084 recovery Methods 0.000 description 1
- 238000012958 reprocessing Methods 0.000 description 1
- 230000000717 retained effect Effects 0.000 description 1
- 238000000926 separation method Methods 0.000 description 1
- 229910052708 sodium Inorganic materials 0.000 description 1
- 239000011734 sodium Substances 0.000 description 1
- 239000012798 spherical particle Substances 0.000 description 1
- 230000001988 toxicity Effects 0.000 description 1
- 231100000419 toxicity Toxicity 0.000 description 1
- AAORDHMTTHGXCV-UHFFFAOYSA-N uranium(6+) Chemical compound [U+6] AAORDHMTTHGXCV-UHFFFAOYSA-N 0.000 description 1
- 238000005406 washing Methods 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
- C04B35/00—Shaped ceramic products characterised by their composition; Ceramics compositions; Processing powders of inorganic compounds preparatory to the manufacturing of ceramic products
- C04B35/51—Shaped ceramic products characterised by their composition; Ceramics compositions; Processing powders of inorganic compounds preparatory to the manufacturing of ceramic products based on compounds of actinides
-
- 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
- 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
-
- 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
- Y10—TECHNICAL SUBJECTS COVERED BY FORMER USPC
- Y10S—TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y10S376/00—Induced nuclear reactions: processes, systems, and elements
- Y10S376/90—Particular material or material shapes for fission reactors
- Y10S376/901—Fuel
Landscapes
- Engineering & Computer Science (AREA)
- Physics & Mathematics (AREA)
- Chemical & Material Sciences (AREA)
- Ceramic Engineering (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Manufacturing & Machinery (AREA)
- Materials Engineering (AREA)
- Structural Engineering (AREA)
- Organic Chemistry (AREA)
- Inorganic Compounds Of Heavy Metals (AREA)
Applications Claiming Priority (2)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| DEP2713108.4 | 1977-03-24 | ||
| DE2713108A DE2713108C2 (de) | 1977-03-24 | 1977-03-24 | Verfahren zur Herstellung von keramischem Plutonium-Uran-Kernbrennstoff in Form von Sinterpellets |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CA1107054A true CA1107054A (en) | 1981-08-18 |
Family
ID=6004604
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CA299,340A Expired CA1107054A (en) | 1977-03-24 | 1978-03-20 | Process for the production of ceramic plutonium uranium nuclear fuel in the form of sintered pellets |
Country Status (10)
| Country | Link |
|---|---|
| US (1) | US4231976A (en, 2012) |
| JP (1) | JPS53118698A (en, 2012) |
| BE (1) | BE865230A (en, 2012) |
| CA (1) | CA1107054A (en, 2012) |
| CH (1) | CH640077A5 (en, 2012) |
| DE (1) | DE2713108C2 (en, 2012) |
| FR (1) | FR2385188A1 (en, 2012) |
| IT (1) | IT1093554B (en, 2012) |
| LU (1) | LU79302A1 (en, 2012) |
| NL (1) | NL189831C (en, 2012) |
Families Citing this family (16)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| IT1096285B (it) * | 1978-05-05 | 1985-08-26 | Agipnucleare S P A Comitato Na | Metodo di fabbricazione di pastiglie di materiale ceramico |
| US4293507A (en) * | 1978-05-26 | 1981-10-06 | United Kingdom Atomic Energy Authority | Preparation of shaped bodies |
| US4261934A (en) * | 1978-11-30 | 1981-04-14 | Electric Power Research Institute, Inc. | Method for homogenizing mixed oxide nuclear fuels |
| DE2921146C2 (de) * | 1979-05-25 | 1982-11-04 | Nukem Gmbh, 6450 Hanau | Verfahren zur Herstellung von keramischen Brennstofftabletten für Kernreaktoren |
| US4397778A (en) * | 1981-01-09 | 1983-08-09 | Lloyd Milton H | Coprocessed nuclear fuels containing (U, Pu) values as oxides, carbides or carbonitrides |
| JPS59232499A (ja) * | 1983-06-15 | 1984-12-27 | 松下電器産業株式会社 | 電子部品供給装置 |
| US5068082A (en) * | 1987-07-18 | 1991-11-26 | Kabushiki Kaisha Toshiba | Fuel assembly for nuclear reactor |
| US5320786A (en) * | 1991-11-27 | 1994-06-14 | The United States Of America As Represented By The Department Of Energy | Zone sintering of ceramic fuels |
| DE19633312A1 (de) * | 1996-08-19 | 1998-02-26 | Siemens Ag | Verfahren zum Sintern von Pellets aus Nuklearbrennstoff |
| GB2330685A (en) * | 1997-10-25 | 1999-04-28 | British Nuclear Fuels Plc | Production of plutonium containing products |
| FR2827072B1 (fr) * | 2001-07-04 | 2005-12-02 | Commissariat Energie Atomique | Procede de fabrication d'un materiau combustible nucleaire composite constitue d'amas d'(u,pu)o2 disperses dans une matrice de uo2 |
| US20050286676A1 (en) * | 2004-06-29 | 2005-12-29 | Lahoda Edward J | Use of isotopically enriched nitride in actinide fuel in nuclear reactors |
| US20070064861A1 (en) * | 2005-08-22 | 2007-03-22 | Battelle Energy Alliance, Llc | High-density, solid solution nuclear fuel and fuel block utilizing same |
| US8085894B2 (en) * | 2007-04-23 | 2011-12-27 | Lawrence Livermore National Security, Llc | Swelling-resistant nuclear fuel |
| FR2949598B1 (fr) * | 2009-09-02 | 2013-03-29 | Commissariat Energie Atomique | Procede de preparation d'un combustible nucleaire poreux a base d'au moins un actinide mineur |
| CN115050499B (zh) * | 2022-06-27 | 2024-12-17 | 中国核动力研究设计院 | 一种全陶瓷包覆燃料及制备方法 |
Family Cites Families (15)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| BE592293A (en, 2012) * | 1959-06-26 | |||
| FR1352519A (fr) * | 1962-04-02 | 1964-02-14 | Atomic Energy Authority Uk | Combustibles pour réacteurs nucléaires |
| US3331783A (en) * | 1964-04-02 | 1967-07-18 | Grace W R & Co | Microspheres containing colloidal carbon |
| US3310386A (en) * | 1965-09-10 | 1967-03-21 | Milton H Lloyd | Preparation of plutonium oxide sol and calcined microspheres |
| US3531416A (en) * | 1967-02-25 | 1970-09-29 | Power Reactor & Nuclear Fuel | Process for producing uo2-puo2 oxide compositions |
| GB1274112A (en) * | 1969-01-08 | 1972-05-10 | Snam Progetti | Improvements in or relating to the production of refractory material |
| US3714056A (en) * | 1969-10-06 | 1973-01-30 | Atomic Energy Commission | Method for preparing stable urania-plutonia sols |
| DE2208672A1 (de) * | 1971-03-04 | 1972-09-14 | General Electric Co., Schenectady, N.Y. (V.StA.) | Brennstoff-Zusammensetzung für Kernreaktoren |
| NL7106712A (en, 2012) * | 1971-05-17 | 1972-11-21 | ||
| JPS4828275A (en, 2012) * | 1971-08-17 | 1973-04-14 | ||
| BE781180A (fr) * | 1972-03-24 | 1972-07-17 | Centre Etd Energie Nucleaire | Procede de fabrication de pastilles de precision |
| GB1461264A (en, 2012) * | 1973-01-12 | 1977-01-13 | ||
| SE387188B (sv) * | 1974-12-05 | 1976-08-30 | Asea Atom Ab | Blandoxidbrensle innehallande uran- och plutoniumdioxid samt forfarande for tillverkning av ett dylikt brensle |
| US4016226A (en) * | 1975-02-10 | 1977-04-05 | The Babcock & Wilcox Company | Method of making porous nuclear fuel |
| CA1023935A (en) * | 1975-02-28 | 1978-01-10 | Her Majesty In Right Of Canada As Represented By Atomic Energy Of Canada Limited | Preparation of mixed oxide nuclear fuel |
-
1977
- 1977-03-24 DE DE2713108A patent/DE2713108C2/de not_active Expired
-
1978
- 1978-03-01 CH CH217978A patent/CH640077A5/de not_active IP Right Cessation
- 1978-03-09 IT IT21012/78A patent/IT1093554B/it active
- 1978-03-09 NL NLAANVRAGE7802616,A patent/NL189831C/xx not_active IP Right Cessation
- 1978-03-14 US US05/886,462 patent/US4231976A/en not_active Expired - Lifetime
- 1978-03-20 CA CA299,340A patent/CA1107054A/en not_active Expired
- 1978-03-22 JP JP3180378A patent/JPS53118698A/ja active Granted
- 1978-03-22 FR FR7808336A patent/FR2385188A1/fr active Granted
- 1978-03-23 LU LU79302A patent/LU79302A1/de unknown
- 1978-03-23 BE BE186202A patent/BE865230A/xx not_active IP Right Cessation
Also Published As
| Publication number | Publication date |
|---|---|
| IT7821012A0 (it) | 1978-03-09 |
| US4231976A (en) | 1980-11-04 |
| FR2385188B1 (en, 2012) | 1981-07-03 |
| NL189831B (nl) | 1993-03-01 |
| IT1093554B (it) | 1985-07-19 |
| LU79302A1 (de) | 1978-06-29 |
| JPS6126637B2 (en, 2012) | 1986-06-21 |
| BE865230A (fr) | 1978-07-17 |
| FR2385188A1 (fr) | 1978-10-20 |
| NL7802616A (nl) | 1978-09-26 |
| DE2713108A1 (de) | 1978-10-05 |
| JPS53118698A (en) | 1978-10-17 |
| NL189831C (nl) | 1993-08-02 |
| DE2713108C2 (de) | 1985-08-14 |
| CH640077A5 (de) | 1983-12-15 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CA1107054A (en) | Process for the production of ceramic plutonium uranium nuclear fuel in the form of sintered pellets | |
| US3504058A (en) | Process for manufacturing sintered pellets of nuclear fuel | |
| US11984232B2 (en) | Process for rapid processing of SiC and graphitic matrix TRISO-bearing pebble fuels | |
| US4364859A (en) | Method for producing oxide powder | |
| EP2082401B1 (de) | Kugelförmiges brennelement und dessen herstellung für gasgekühlte hochtemperatur-kugelhaufen-kernreaktoren (htr) | |
| US3992258A (en) | Coated nuclear fuel particles and process for making the same | |
| US3011960A (en) | Methods of manufacturing graphite bodies and nuclear fuel materials comprising said graphite bodies | |
| US3179723A (en) | Method of forming metal carbide spheroids with carbon coat | |
| KR20040029408A (ko) | 혼합산화물 핵연료 분말 및 혼합산화물 핵연료 소결체의제조 방법 | |
| Ganguly et al. | Sol-Gel microsphere pelletization process for fabrication of high-density ThO2—2% UO2 fuel for advanced pressurized heavy water reactors | |
| US3243349A (en) | Carbon coated, metal carbide particles for nuclear reactor use | |
| US3668283A (en) | Process for the fabrication of nuclear fuel elements | |
| US3270098A (en) | Method of making hollow, spherical uo2 particles | |
| Lahr | Fabrication, properties, and irradiation behavior of U/Pu particle fuel for light water reactors | |
| MacLeod et al. | Development of mixed-oxide fuel manufacture in the United Kingdom and the influence of fuel characteristics on irradiation performance | |
| US6733699B1 (en) | Method for producing nuclear fuel pellets of the MOX type | |
| US20200027586A1 (en) | Manufacture of Large Grain Powders with Granular Coatings | |
| GB1599857A (en) | Process for the production of ceramic plutonium-uranium nuclear fuel in the form of sintered pellets | |
| US3404200A (en) | Method of preparing a cermet nuclear fuel | |
| Gündüz et al. | Effects of Different Parameters on the Densities of Uranium Dioxide and Uranium Dioxide–Gadolinium Oxide Fuels Produced by the Sol-Gel Technique | |
| US3294698A (en) | Hollow, spherical uo2 nuclear fuel particles | |
| US3254030A (en) | Plutonium enriched uranium fuel for nuclear reactors | |
| US3271265A (en) | Fuels for nuclear reactors | |
| Radford et al. | Fabrication development and application of an annular Al2O3-B4C burnable absorber | |
| RU2672256C1 (ru) | Таблетка для изготовления тепловыделяющего элемента ядерного реактора на быстрых нейтронах |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| MKEX | Expiry |