DE1270700B - Betriebsverfahren fuer einen gasgekuehlten Atomkernreaktor mit Graphitmoderator - Google Patents
Betriebsverfahren fuer einen gasgekuehlten Atomkernreaktor mit GraphitmoderatorInfo
- Publication number
- DE1270700B DE1270700B DEP1270A DE1270700A DE1270700B DE 1270700 B DE1270700 B DE 1270700B DE P1270 A DEP1270 A DE P1270A DE 1270700 A DE1270700 A DE 1270700A DE 1270700 B DE1270700 B DE 1270700B
- Authority
- DE
- Germany
- Prior art keywords
- graphite
- reactor
- wigner
- growth
- irradiation
- 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.)
- Pending
Links
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 title claims description 96
- 229910002804 graphite Inorganic materials 0.000 title claims description 94
- 239000010439 graphite Substances 0.000 title claims description 94
- 238000011017 operating method Methods 0.000 title claims description 7
- 238000000034 method Methods 0.000 claims description 16
- 230000001186 cumulative effect Effects 0.000 claims description 8
- 238000010438 heat treatment Methods 0.000 claims description 7
- 230000000737 periodic effect Effects 0.000 claims description 5
- 238000005516 engineering process Methods 0.000 claims description 2
- 230000006641 stabilisation Effects 0.000 claims description 2
- 238000011105 stabilization Methods 0.000 claims description 2
- 230000005855 radiation Effects 0.000 description 25
- 238000011084 recovery Methods 0.000 description 20
- 238000011282 treatment Methods 0.000 description 20
- 238000005496 tempering Methods 0.000 description 18
- 230000007547 defect Effects 0.000 description 8
- 230000003647 oxidation Effects 0.000 description 7
- 238000007254 oxidation reaction Methods 0.000 description 7
- 230000008569 process Effects 0.000 description 7
- 230000008859 change Effects 0.000 description 6
- 230000008030 elimination Effects 0.000 description 6
- 238000003379 elimination reaction Methods 0.000 description 6
- 238000004146 energy storage Methods 0.000 description 6
- 230000009931 harmful effect Effects 0.000 description 6
- 230000002829 reductive effect Effects 0.000 description 6
- 230000000694 effects Effects 0.000 description 5
- 238000005259 measurement Methods 0.000 description 5
- 230000009467 reduction Effects 0.000 description 5
- 229910052770 Uranium Inorganic materials 0.000 description 4
- 238000000137 annealing Methods 0.000 description 4
- 238000001816 cooling Methods 0.000 description 4
- 230000000191 radiation effect Effects 0.000 description 4
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 description 4
- 238000009825 accumulation Methods 0.000 description 3
- 239000000446 fuel Substances 0.000 description 3
- 238000003860 storage Methods 0.000 description 3
- 230000008901 benefit Effects 0.000 description 2
- 229910052799 carbon Inorganic materials 0.000 description 2
- 125000004432 carbon atom Chemical group C* 0.000 description 2
- 238000006243 chemical reaction Methods 0.000 description 2
- 238000010276 construction Methods 0.000 description 2
- 230000001419 dependent effect Effects 0.000 description 2
- 238000002474 experimental method Methods 0.000 description 2
- 239000000463 material Substances 0.000 description 2
- 238000011160 research Methods 0.000 description 2
- 230000002269 spontaneous effect Effects 0.000 description 2
- 230000035882 stress Effects 0.000 description 2
- 239000002699 waste material Substances 0.000 description 2
- 230000002411 adverse Effects 0.000 description 1
- 230000032683 aging Effects 0.000 description 1
- 230000033228 biological regulation Effects 0.000 description 1
- 230000001680 brushing effect Effects 0.000 description 1
- 230000015556 catabolic process Effects 0.000 description 1
- 238000003776 cleavage reaction Methods 0.000 description 1
- 230000001595 contractor effect Effects 0.000 description 1
- 239000013078 crystal Substances 0.000 description 1
- 230000007423 decrease Effects 0.000 description 1
- 230000003247 decreasing effect Effects 0.000 description 1
- 238000006731 degradation reaction Methods 0.000 description 1
- 238000006073 displacement reaction Methods 0.000 description 1
- 230000004992 fission Effects 0.000 description 1
- 238000005755 formation reaction Methods 0.000 description 1
- 230000002427 irreversible effect Effects 0.000 description 1
- 239000008141 laxative Substances 0.000 description 1
- 230000002475 laxative effect Effects 0.000 description 1
- 238000004519 manufacturing process Methods 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 239000003758 nuclear fuel Substances 0.000 description 1
- 230000003287 optical effect Effects 0.000 description 1
- 230000036961 partial effect Effects 0.000 description 1
- 230000002265 prevention Effects 0.000 description 1
- 238000010791 quenching Methods 0.000 description 1
- 230000000171 quenching effect Effects 0.000 description 1
- 230000009257 reactivity Effects 0.000 description 1
- 230000007017 scission Effects 0.000 description 1
- 238000012360 testing method Methods 0.000 description 1
- 229910052724 xenon Inorganic materials 0.000 description 1
- FHNFHKCVQCLJFQ-UHFFFAOYSA-N xenon atom Chemical compound [Xe] FHNFHKCVQCLJFQ-UHFFFAOYSA-N 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
- G21C5/02—Details
- G21C5/08—Means for preventing undesired asymmetric expansion of the complete structure ; Stretching devices, pins
-
- 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
- G21C5/126—Carbonic moderators
-
- 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)
- Carbon And Carbon Compounds (AREA)
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| US219088A US3183166A (en) | 1962-08-23 | 1962-08-23 | Low temperature graphite radiation damage removal |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| DE1270700B true DE1270700B (de) | 1968-06-20 |
Family
ID=22817827
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| DEP1270A Pending DE1270700B (de) | 1962-08-23 | 1963-07-24 | Betriebsverfahren fuer einen gasgekuehlten Atomkernreaktor mit Graphitmoderator |
Country Status (5)
Families Citing this family (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US3320134A (en) * | 1963-07-05 | 1967-05-16 | Atomic Energy Authority Uk | Method of reducing carbon loss from graphite moderator in carbon dioxidecooled nuclear reactor |
| JPS51117295A (en) * | 1975-04-07 | 1976-10-15 | Hitachi Ltd | Process of operating a nuclear reactor |
-
0
- NL NL296960D patent/NL296960A/xx unknown
- BE BE635580D patent/BE635580A/xx unknown
-
1962
- 1962-08-23 US US219088A patent/US3183166A/en not_active Expired - Lifetime
-
1963
- 1963-06-17 GB GB23947/63A patent/GB999931A/en not_active Expired
- 1963-07-24 DE DEP1270A patent/DE1270700B/de active Pending
Non-Patent Citations (1)
| Title |
|---|
| None * |
Also Published As
| Publication number | Publication date |
|---|---|
| US3183166A (en) | 1965-05-11 |
| GB999931A (en) | 1965-07-28 |
| NL296960A (GUID-C5D7CC26-194C-43D0-91A1-9AE8C70A9BFF.html) | |
| BE635580A (GUID-C5D7CC26-194C-43D0-91A1-9AE8C70A9BFF.html) |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| DE2515709C2 (GUID-C5D7CC26-194C-43D0-91A1-9AE8C70A9BFF.html) | ||
| DE69511306T2 (de) | Kernreaktorbrennstoffbündel und Verfahren zur Herstellung | |
| DE69432775T2 (de) | Verfahren zur Herstellung von Zircaloy Rohren mit hohem Widerstand gegen Rissausbreitung | |
| DE2535654C2 (GUID-C5D7CC26-194C-43D0-91A1-9AE8C70A9BFF.html) | ||
| DE1589801A1 (de) | Brennstoffbuendel fuer Kernreaktoren | |
| DE2715433A1 (de) | Verfahren zum schnellabsenken der leistung eines kernreaktors | |
| DE1589824C3 (de) | Verfahren zum Betrieb eines Kernreaktors | |
| EP1760724A2 (de) | Brennelement für einen Druckwasser-Reaktor und Verfahren zur Herstellung seiner Hüllrohre | |
| DE2531396A1 (de) | System zur regelung der ausgangsleistung von siedewasserreaktoren | |
| DE1467294A1 (de) | Kernreaktor-Brennstoff | |
| DE2753488C2 (de) | Verfahren zur Herstellung von n-dotiertem Silicium durch Neutronenbestrahlung | |
| DE2516123C3 (de) | Verfahren zum Abführen der Zerfallswärme radioaktiver Spaltprodukte | |
| DE1154878B (de) | Verfahren zur Herstellung von Halbleiterkoerpern fuer Halbleiteranordnungen aus n-leitendem Silizium durch Bestrahlen mit thermischen Neutronen | |
| DE2612178A1 (de) | Verfahren zum abschalten und regeln eines gasgekuehlten kernreaktors | |
| DE1270700B (de) | Betriebsverfahren fuer einen gasgekuehlten Atomkernreaktor mit Graphitmoderator | |
| DE69702222T3 (de) | Zirkonlegierung mit niedrigem Bestrahlungswachstum, deren Herstellungsverfahren und Verwendung | |
| DE2643092A1 (de) | Verbesserter thermischer oder epithermischer reaktor | |
| DE2451748A1 (de) | Gasgekuehlter kernreaktor und verfahren zum steuern und regeln des reaktors | |
| DE2455894A1 (de) | Stahllegierung | |
| DE69901597T2 (de) | Neutronenabsorbierendes verbundmaterial und herstellungsverfahren dafür | |
| DE2352691C2 (de) | Gasgekühlter Kernreaktor mit einer Schüttung von kugelförmigen Brennelementen | |
| DE2116937C3 (de) | Verfahren zur Erprobung von Brennelementen für Kernreaktoren | |
| DE2551512A1 (de) | Verfahren zur herstellung eines brennstoffelements fuer einen gasgekuehlten hochtemperatur-reaktor | |
| DE68910879T2 (de) | Spaltzonenkomponente eines Kernreaktors und Betriebsmethode für einen Kernreaktor. | |
| DE2752028A1 (de) | Gasgekuehlter graphitmoderierter kernreaktor |