NO117432B - - Google Patents
Download PDFInfo
- Publication number
- NO117432B NO117432B NO1351/68A NO135168A NO117432B NO 117432 B NO117432 B NO 117432B NO 1351/68 A NO1351/68 A NO 1351/68A NO 135168 A NO135168 A NO 135168A NO 117432 B NO117432 B NO 117432B
- Authority
- NO
- Norway
- Prior art keywords
- plates
- zirconium
- steel
- plate
- neutron absorber
- Prior art date
Links
- 239000006096 absorbing agent Substances 0.000 claims description 22
- 229910000831 Steel Inorganic materials 0.000 claims description 16
- 239000002131 composite material Substances 0.000 claims description 16
- 239000010959 steel Substances 0.000 claims description 16
- QCWXUUIWCKQGHC-UHFFFAOYSA-N Zirconium Chemical compound [Zr] QCWXUUIWCKQGHC-UHFFFAOYSA-N 0.000 claims description 12
- 229910052726 zirconium Inorganic materials 0.000 claims description 12
- 229910001093 Zr alloy Inorganic materials 0.000 claims description 11
- ZOXJGFHDIHLPTG-UHFFFAOYSA-N Boron Chemical compound [B] ZOXJGFHDIHLPTG-UHFFFAOYSA-N 0.000 claims description 9
- 229910052796 boron Inorganic materials 0.000 claims description 9
- 239000004020 conductor Substances 0.000 claims description 8
- 239000002826 coolant Substances 0.000 claims description 8
- 239000000463 material Substances 0.000 claims description 8
- 229910001220 stainless steel Inorganic materials 0.000 claims description 8
- 239000010935 stainless steel Substances 0.000 claims description 8
- 238000000034 method Methods 0.000 claims description 5
- 238000004519 manufacturing process Methods 0.000 claims description 4
- 238000007493 shaping process Methods 0.000 claims description 2
- ZOXJGFHDIHLPTG-BJUDXGSMSA-N Boron-10 Chemical compound [10B] ZOXJGFHDIHLPTG-BJUDXGSMSA-N 0.000 claims 2
- 239000000446 fuel Substances 0.000 description 28
- 238000003466 welding Methods 0.000 description 7
- 230000009257 reactivity Effects 0.000 description 6
- 229910000712 Boron steel Inorganic materials 0.000 description 4
- XLYOFNOQVPJJNP-ZSJDYOACSA-N Heavy water Chemical compound [2H]O[2H] XLYOFNOQVPJJNP-ZSJDYOACSA-N 0.000 description 4
- 238000009826 distribution Methods 0.000 description 4
- 230000008901 benefit Effects 0.000 description 3
- 230000004907 flux Effects 0.000 description 3
- 230000008569 process Effects 0.000 description 3
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 3
- 229910045601 alloy Inorganic materials 0.000 description 2
- 239000000956 alloy Substances 0.000 description 2
- 239000000498 cooling water Substances 0.000 description 2
- 238000010894 electron beam technology Methods 0.000 description 2
- 239000007788 liquid Substances 0.000 description 2
- 230000008929 regeneration Effects 0.000 description 2
- 238000011069 regeneration method Methods 0.000 description 2
- 229910052692 Dysprosium Inorganic materials 0.000 description 1
- 229910052691 Erbium Inorganic materials 0.000 description 1
- 229910052688 Gadolinium Inorganic materials 0.000 description 1
- GRYLNZFGIOXLOG-UHFFFAOYSA-N Nitric acid Chemical compound O[N+]([O-])=O GRYLNZFGIOXLOG-UHFFFAOYSA-N 0.000 description 1
- 229910000589 SAE 304 stainless steel Inorganic materials 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- 238000009835 boiling Methods 0.000 description 1
- 238000005352 clarification Methods 0.000 description 1
- 238000004140 cleaning Methods 0.000 description 1
- 239000004035 construction material Substances 0.000 description 1
- KBQHZAAAGSGFKK-UHFFFAOYSA-N dysprosium atom Chemical compound [Dy] KBQHZAAAGSGFKK-UHFFFAOYSA-N 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- UYAHIZSMUZPPFV-UHFFFAOYSA-N erbium Chemical compound [Er] UYAHIZSMUZPPFV-UHFFFAOYSA-N 0.000 description 1
- UIWYJDYFSGRHKR-UHFFFAOYSA-N gadolinium atom Chemical compound [Gd] UIWYJDYFSGRHKR-UHFFFAOYSA-N 0.000 description 1
- 238000010438 heat treatment Methods 0.000 description 1
- 238000011835 investigation Methods 0.000 description 1
- 230000007774 longterm Effects 0.000 description 1
- 238000010297 mechanical methods and process Methods 0.000 description 1
- 229910052751 metal Inorganic materials 0.000 description 1
- 239000002184 metal Substances 0.000 description 1
- 150000002739 metals Chemical class 0.000 description 1
- 239000000203 mixture Substances 0.000 description 1
- 229910017604 nitric acid Inorganic materials 0.000 description 1
- 230000008520 organization Effects 0.000 description 1
- 229910052761 rare earth metal Inorganic materials 0.000 description 1
- 238000005096 rolling process Methods 0.000 description 1
- 239000000126 substance Substances 0.000 description 1
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C7/00—Control of nuclear reaction
- G21C7/02—Control of nuclear reaction by using self-regulating properties of reactor materials, e.g. Doppler effect
- G21C7/04—Control of nuclear reaction by using self-regulating properties of reactor materials, e.g. Doppler effect of burnable poisons
-
- 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
- G21C3/06—Casings; Jackets
-
- 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)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Priority Applications (4)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| NO1351/68A NO117432B (fr) | 1968-04-06 | 1968-04-06 | |
| SE4747/69A SE345336B (fr) | 1968-04-06 | 1969-04-02 | |
| US813296A US3663366A (en) | 1968-04-06 | 1969-04-03 | Shroud for a fuel assembly in a nuclear reactor |
| DE19691918251 DE1918251A1 (de) | 1968-04-06 | 1969-04-03 | Huelle fuer Brennstoffelement eines Kernreaktors und Verfahren zu ihrer Herstellung |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| NO1351/68A NO117432B (fr) | 1968-04-06 | 1968-04-06 |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| NO117432B true NO117432B (fr) | 1969-08-11 |
Family
ID=19878149
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| NO1351/68A NO117432B (fr) | 1968-04-06 | 1968-04-06 |
Country Status (4)
| Country | Link |
|---|---|
| US (1) | US3663366A (fr) |
| DE (1) | DE1918251A1 (fr) |
| NO (1) | NO117432B (fr) |
| SE (1) | SE345336B (fr) |
Families Citing this family (9)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4011133A (en) * | 1975-07-16 | 1977-03-08 | The United States Of America As Represented By The United States Energy Research And Development Administration | Austenitic stainless steel alloys having improved resistance to fast neutron-induced swelling |
| US4626404A (en) * | 1983-12-21 | 1986-12-02 | Westinghouse Electric Corp. | Annular burnable absorber rod |
| US4640813A (en) * | 1984-09-26 | 1987-02-03 | Westinghouse Electric Corp. | Soluble burnable absorber rod for a nuclear reactor |
| CH668471A5 (de) * | 1985-10-11 | 1988-12-30 | Koch Ag | Kuehlschrank, insbesondere zur verwendung als leih-kuehlschrank. |
| US4818471A (en) * | 1987-08-10 | 1989-04-04 | Westinghouse Electric Corp. | BWR fuel assembly channel with localized neutron absorber strips for LPRM calibration |
| WO1997004462A1 (fr) * | 1995-07-19 | 1997-02-06 | Sigmunt Rottenberg | Reacteur nucleaire miniaturise avec elements structuraux de tubes de force ameliores |
| US5640434A (en) * | 1995-07-31 | 1997-06-17 | Rottenberg; Sigmunt | Miniaturized nuclear reactor utilizing improved pressure tube structural members |
| JP3419997B2 (ja) * | 1996-06-26 | 2003-06-23 | 株式会社日立製作所 | 燃料集合体と該燃料集合体用のチャンネルボックスの製造方法 |
| US8532245B2 (en) * | 2008-12-17 | 2013-09-10 | Westinghouse Electric Company Llc | Core shroud corner joints |
Family Cites Families (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US3049484A (en) * | 1957-10-31 | 1962-08-14 | Curtiss Wright Corp | Apparatus for production of radioactive isotopes |
| NL245961A (fr) * | 1958-03-14 | 1900-01-01 | ||
| US3175955A (en) * | 1961-01-11 | 1965-03-30 | Richard D Cheverton | Gradient fuel plates |
| BE635037A (fr) * | 1962-07-16 |
-
1968
- 1968-04-06 NO NO1351/68A patent/NO117432B/no unknown
-
1969
- 1969-04-02 SE SE4747/69A patent/SE345336B/xx unknown
- 1969-04-03 US US813296A patent/US3663366A/en not_active Expired - Lifetime
- 1969-04-03 DE DE19691918251 patent/DE1918251A1/de active Pending
Also Published As
| Publication number | Publication date |
|---|---|
| US3663366A (en) | 1972-05-16 |
| SE345336B (fr) | 1972-05-23 |
| DE1918251A1 (de) | 1970-01-22 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| US5297177A (en) | Fuel assembly, components thereof and method of manufacture | |
| NO117432B (fr) | ||
| GB885891A (en) | Composite nuclear fuel element and nuclear reactor incorporating the same | |
| Park et al. | HYPER (Hybrid Power Extraction Reactor): A system for clean nuclear energy | |
| DE1068821B (fr) | ||
| Brumovský | WWER RPV Surveillance Programs | |
| Cheverton et al. | An embrittlement rate effect deduced from HFIR that may impact LWR vessel support life expectancy | |
| NO133808B (fr) | ||
| Rebak et al. | Anticipated Improved Performance of Advanced Steel Cladding Under Long Term Dry Storage of Spent Fuel | |
| Marston et al. | Radiation embrittlement: significance of its effects on integrity and operation of LWR pressure vessels | |
| Bean et al. | Roll Cladding Uranium-Zirconium and Uranium-Zirconium-Niobium Alloys with Zircaloy-2 for Plate-type Fuel Elements | |
| Bishop | BRADWELL REACTOR VESSELS. DESIGN, FABRICATION AND ERECTION PROBLEMS | |
| Veteau | ARTEMIS program: Investigation of MCCI by means of simulating material experiments | |
| Addison et al. | IRRADIATED NUCLEAR FUEL STORAGE AT THE SELLAFTELD (UK) REPROCESSING PLANT | |
| CN105427899B (zh) | 反应堆器件辐射损伤的热处理恢复技术 | |
| Goodwin et al. | ANALYSIS OF PWR FUEL ROD DEVELOPMENT PROCTESSES. | |
| Farina et al. | Current status of Zirconium alloys for fission cladding | |
| Guichard et al. | Preparation of uranium rods by continuous casting under vacuum | |
| Sasaki et al. | STUDIES ON THE CONTAINER FOR DISPOSING RADIOACTIVE WASTES INTO THE SEA. PART I | |
| Rousseau | High yield strength steels for nuclear reactors | |
| Spedding et al. | ALLOY FOR USE IN NUCLEAR FISSION | |
| Zinn et al. | CONTROL ROD | |
| Surya Rao et al. | HOW CIR TEAM SOLVED CORROSION, DEPOSITION PROBLEMS | |
| Woodhouse | Development of tubular fuel and target elements for Savannah River | |
| Fizzotti et al. | DEVELOPMENT OF FUEL ELEMENT FABRICATION TECHNIQUE FOR URANIUM ALLOYS. |