CA1081375A - Utilization of heavy elements such as lead or bismuth in thermal and epithermal reactors - Google Patents
Utilization of heavy elements such as lead or bismuth in thermal and epithermal reactorsInfo
- Publication number
- CA1081375A CA1081375A CA261,768A CA261768A CA1081375A CA 1081375 A CA1081375 A CA 1081375A CA 261768 A CA261768 A CA 261768A CA 1081375 A CA1081375 A CA 1081375A
- Authority
- CA
- Canada
- Prior art keywords
- heavy
- reactor
- fuel
- heavy element
- rods
- 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
- 229910052797 bismuth Inorganic materials 0.000 title claims abstract description 33
- JCXGWMGPZLAOME-UHFFFAOYSA-N bismuth atom Chemical compound [Bi] JCXGWMGPZLAOME-UHFFFAOYSA-N 0.000 title claims abstract description 33
- XLYOFNOQVPJJNP-ZSJDYOACSA-N Heavy water Chemical compound [2H]O[2H] XLYOFNOQVPJJNP-ZSJDYOACSA-N 0.000 claims abstract description 96
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims abstract description 52
- 230000009257 reactivity Effects 0.000 claims abstract description 27
- 238000006243 chemical reaction Methods 0.000 claims abstract description 6
- 239000000446 fuel Substances 0.000 claims description 74
- 150000001875 compounds Chemical class 0.000 claims description 7
- 239000000203 mixture Substances 0.000 claims description 7
- 239000003758 nuclear fuel Substances 0.000 claims description 4
- 239000000463 material Substances 0.000 description 15
- 230000004992 fission Effects 0.000 description 8
- 238000001228 spectrum Methods 0.000 description 8
- 238000003780 insertion Methods 0.000 description 6
- 230000037431 insertion Effects 0.000 description 6
- 229910052739 hydrogen Inorganic materials 0.000 description 5
- 239000001257 hydrogen Substances 0.000 description 5
- UFHFLCQGNIYNRP-UHFFFAOYSA-N Hydrogen Chemical compound [H][H] UFHFLCQGNIYNRP-UHFFFAOYSA-N 0.000 description 4
- 238000004364 calculation method Methods 0.000 description 4
- 238000001816 cooling Methods 0.000 description 4
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 description 4
- 238000010521 absorption reaction Methods 0.000 description 3
- 239000002826 coolant Substances 0.000 description 3
- 238000002844 melting Methods 0.000 description 3
- 230000008018 melting Effects 0.000 description 3
- 239000011800 void material Substances 0.000 description 3
- OYEHPCDNVJXUIW-FTXFMUIASA-N 239Pu Chemical compound [239Pu] OYEHPCDNVJXUIW-FTXFMUIASA-N 0.000 description 2
- 229910052770 Uranium Inorganic materials 0.000 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 description 2
- 125000004429 atom Chemical group 0.000 description 2
- WMWLMWRWZQELOS-UHFFFAOYSA-N bismuth(iii) oxide Chemical compound O=[Bi]O[Bi]=O WMWLMWRWZQELOS-UHFFFAOYSA-N 0.000 description 2
- 238000009835 boiling Methods 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- 229910000439 uranium oxide Inorganic materials 0.000 description 2
- JFALSRSLKYAFGM-FTXFMUIASA-N uranium-233 Chemical compound [233U] JFALSRSLKYAFGM-FTXFMUIASA-N 0.000 description 2
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 description 1
- YZCKVEUIGOORGS-OUBTZVSYSA-N Deuterium Chemical compound [2H] YZCKVEUIGOORGS-OUBTZVSYSA-N 0.000 description 1
- HZEBHPIOVYHPMT-OUBTZVSYSA-N Polonium-210 Chemical compound [210Po] HZEBHPIOVYHPMT-OUBTZVSYSA-N 0.000 description 1
- QCWXUUIWCKQGHC-UHFFFAOYSA-N Zirconium Chemical compound [Zr] QCWXUUIWCKQGHC-UHFFFAOYSA-N 0.000 description 1
- 229910052790 beryllium Inorganic materials 0.000 description 1
- ATBAMAFKBVZNFJ-UHFFFAOYSA-N beryllium atom Chemical compound [Be] ATBAMAFKBVZNFJ-UHFFFAOYSA-N 0.000 description 1
- 230000015572 biosynthetic process Effects 0.000 description 1
- 230000015556 catabolic process Effects 0.000 description 1
- 229910052729 chemical element Inorganic materials 0.000 description 1
- 238000005253 cladding Methods 0.000 description 1
- 230000002860 competitive effect Effects 0.000 description 1
- 230000003247 decreasing effect Effects 0.000 description 1
- 238000006731 degradation reaction Methods 0.000 description 1
- 229910052805 deuterium Inorganic materials 0.000 description 1
- 238000013213 extrapolation Methods 0.000 description 1
- 230000004907 flux Effects 0.000 description 1
- 229910002804 graphite Inorganic materials 0.000 description 1
- 239000010439 graphite Substances 0.000 description 1
- 238000010438 heat treatment Methods 0.000 description 1
- 150000002431 hydrogen Chemical class 0.000 description 1
- WABPQHHGFIMREM-UHFFFAOYSA-N lead(0) Chemical compound [Pb] WABPQHHGFIMREM-UHFFFAOYSA-N 0.000 description 1
- 230000001818 nuclear effect Effects 0.000 description 1
- 230000003071 parasitic effect Effects 0.000 description 1
- 239000002574 poison Substances 0.000 description 1
- 231100000614 poison Toxicity 0.000 description 1
- 239000013589 supplement Substances 0.000 description 1
- 230000002459 sustained effect Effects 0.000 description 1
- ZSLUVFAKFWKJRC-UHFFFAOYSA-N thorium Chemical compound [Th] ZSLUVFAKFWKJRC-UHFFFAOYSA-N 0.000 description 1
- 231100000331 toxic Toxicity 0.000 description 1
- 230000002588 toxic effect Effects 0.000 description 1
- JFALSRSLKYAFGM-OIOBTWANSA-N uranium-235 Chemical compound [235U] JFALSRSLKYAFGM-OIOBTWANSA-N 0.000 description 1
- 229910052726 zirconium Inorganic materials 0.000 description 1
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C5/00—Moderator or core structure; Selection of materials for use as moderator
- G21C5/12—Moderator or core structure; Selection of materials for use as moderator characterised by composition, e.g. the moderator containing additional substances which ensure improved heat resistance of the moderator
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C1/00—Reactor types
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C1/00—Reactor types
- G21C1/04—Thermal reactors ; Epithermal reactors
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C1/00—Reactor types
- G21C1/04—Thermal reactors ; Epithermal reactors
- G21C1/06—Heterogeneous reactors, i.e. in which fuel and moderator are separated
-
- 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
- G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
- G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements
- G21C3/326—Bundles of parallel pin-, rod-, or tube-shaped fuel elements comprising fuel elements of different composition; comprising, in addition to the fuel elements, other pin-, rod-, or tube-shaped elements, e.g. control rods, grid support rods, fertile rods, poison rods or dummy rods
- G21C3/328—Relative disposition of the elements in the bundle lattice
-
- 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
- Y10S376/904—Moderator, reflector, or coolant materials
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Particle Accelerators (AREA)
- Production Of Liquid Hydrocarbon Mixture For Refining Petroleum (AREA)
- Catalysts (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| US05/723,482 US4123328A (en) | 1976-09-15 | 1976-09-15 | Utilization of heavy elements in thermal and epithermal reactors |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CA1081375A true CA1081375A (en) | 1980-07-08 |
Family
ID=24906458
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CA261,768A Expired CA1081375A (en) | 1976-09-15 | 1976-09-22 | Utilization of heavy elements such as lead or bismuth in thermal and epithermal reactors |
Country Status (5)
| Country | Link |
|---|---|
| US (1) | US4123328A (enExample) |
| CA (1) | CA1081375A (enExample) |
| DE (1) | DE2643092C3 (enExample) |
| FR (1) | FR2365184A1 (enExample) |
| GB (1) | GB1553980A (enExample) |
Families Citing this family (10)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4881247A (en) * | 1982-03-25 | 1989-11-14 | Westinghouse Electric Corp. | Measuring nuclear fuel burnup |
| US4495136A (en) * | 1982-05-11 | 1985-01-22 | Westinghouse Electric Corp. | Maximum power capability blanket for nuclear reactors |
| US4526741A (en) * | 1983-06-10 | 1985-07-02 | The United States Of America As Represented By The United States Department Of Energy | Fuel assembly for the production of tritium in light water reactors |
| US4699756A (en) * | 1985-08-08 | 1987-10-13 | Westinghouse Electric Corp. | Full length control rod employing axially inhomogeneous absorber materials for zero reactivity redistribution factor |
| US4818478A (en) * | 1987-12-07 | 1989-04-04 | Westinghouse Electric Corp. | BWR fuel assembly mini-bundle having interior fuel rods of reduced diameter |
| US5442668A (en) * | 1993-06-03 | 1995-08-15 | Massachusetts Institute Of Technology | Passive pressure tube light water cooled and moderated reactor |
| US20050069075A1 (en) * | 2003-06-04 | 2005-03-31 | D.B.I. Century Fuels And Aerospace Services, Inc. | Reactor tray vertical geometry with vitrified waste control |
| EP2339589A1 (en) * | 2009-12-25 | 2011-06-29 | Global Nuclear Fuel-Japan Co., Ltd. | Fuel assembly |
| KR101533868B1 (ko) * | 2012-07-24 | 2015-07-06 | 한국원자력연구원 | 중수로 핵연료 다발의 핵연료봉 구조 |
| KR101744156B1 (ko) | 2016-02-29 | 2017-06-07 | (주)뉴클리어엔지니어링 | 개량형 중수로용 핵연료 다발 |
Family Cites Families (11)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US2837477A (en) * | 1945-02-16 | 1958-06-03 | Fermi Enrico | Chain reacting system |
| US2830944A (en) * | 1945-08-28 | 1958-04-15 | Eugene P Wigner | Neutronic reactor |
| US2832733A (en) * | 1946-04-23 | 1958-04-29 | Szilard Leo | Heavy water moderated neutronic reactor |
| US3048534A (en) * | 1952-03-28 | 1962-08-07 | Tonks Lewi | Control means for neutronic reactors |
| GB948909A (en) * | 1959-06-19 | 1964-02-05 | Rolls Royce | Improvements in or relating to nuclear reactors |
| NL279220A (enExample) * | 1962-06-04 | |||
| US3255083A (en) * | 1962-12-26 | 1966-06-07 | Carl N Klahr | Method of flux separation in nuclear reactors and structure therefor |
| US3351532A (en) * | 1965-09-20 | 1967-11-07 | Jr Harry F Raab | Seed-blanket converter-recycle breeder reactor |
| US3523869A (en) * | 1967-10-03 | 1970-08-11 | Byk Gulden Lomberg Chem Fab | Booster-source rods in heavy water moderated reactor |
| US3519535A (en) * | 1968-01-24 | 1970-07-07 | Westinghouse Electric Corp | Nuclear fuel assembly with plural independent control elements and system therefor |
| US3849248A (en) * | 1969-02-14 | 1974-11-19 | Gen Electric | Samarium compensation for nuclear reactor fuel |
-
1976
- 1976-09-15 US US05/723,482 patent/US4123328A/en not_active Expired - Lifetime
- 1976-09-16 GB GB38350/76A patent/GB1553980A/en not_active Expired
- 1976-09-21 FR FR7628336A patent/FR2365184A1/fr active Granted
- 1976-09-22 CA CA261,768A patent/CA1081375A/en not_active Expired
- 1976-09-24 DE DE2643092A patent/DE2643092C3/de not_active Expired
Also Published As
| Publication number | Publication date |
|---|---|
| US4123328A (en) | 1978-10-31 |
| FR2365184B1 (enExample) | 1979-01-12 |
| DE2643092B2 (de) | 1980-05-08 |
| GB1553980A (en) | 1979-10-17 |
| DE2643092A1 (de) | 1978-04-06 |
| FR2365184A1 (fr) | 1978-04-14 |
| DE2643092C3 (de) | 1981-02-05 |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| MKEX | Expiry |