DE1201927B - Leistungsrohr fuer einen Kernreaktor - Google Patents
Leistungsrohr fuer einen KernreaktorInfo
- Publication number
- DE1201927B DE1201927B DEG38357A DEG0038357A DE1201927B DE 1201927 B DE1201927 B DE 1201927B DE G38357 A DEG38357 A DE G38357A DE G0038357 A DEG0038357 A DE G0038357A DE 1201927 B DE1201927 B DE 1201927B
- Authority
- DE
- Germany
- Prior art keywords
- sleeve
- pipe
- reactor
- power
- tube
- 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
- 238000005253 cladding Methods 0.000 claims description 17
- 238000007789 sealing Methods 0.000 claims description 16
- 239000002826 coolant Substances 0.000 claims description 9
- 239000007788 liquid Substances 0.000 claims description 9
- 238000012360 testing method Methods 0.000 claims description 6
- 210000004907 gland Anatomy 0.000 claims description 3
- 238000012856 packing Methods 0.000 claims description 3
- 238000004891 communication Methods 0.000 claims 1
- 238000003780 insertion Methods 0.000 claims 1
- 230000037431 insertion Effects 0.000 claims 1
- 238000012545 processing Methods 0.000 claims 1
- XLYOFNOQVPJJNP-ZSJDYOACSA-N Heavy water Chemical compound [2H]O[2H] XLYOFNOQVPJJNP-ZSJDYOACSA-N 0.000 description 4
- 239000000446 fuel Substances 0.000 description 4
- 238000009413 insulation Methods 0.000 description 4
- 238000001816 cooling Methods 0.000 description 3
- 239000007789 gas Substances 0.000 description 3
- 239000000126 substance Substances 0.000 description 3
- 230000007717 exclusion Effects 0.000 description 2
- 230000004907 flux Effects 0.000 description 2
- 239000007787 solid Substances 0.000 description 2
- 239000000110 cooling liquid Substances 0.000 description 1
- 229920001971 elastomer Polymers 0.000 description 1
- 239000000806 elastomer Substances 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 238000005192 partition Methods 0.000 description 1
- 230000005855 radiation Effects 0.000 description 1
- 239000003566 sealing material Substances 0.000 description 1
- 239000011343 solid material Substances 0.000 description 1
- 229920003002 synthetic resin Polymers 0.000 description 1
- 239000000057 synthetic resin Substances 0.000 description 1
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/20—Partitions or thermal insulation between fuel channel and moderator
-
- 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
- G21C1/14—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor
- G21C1/16—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor moderator and coolant being different or separated, e.g. sodium-graphite reactor, sodium-heavy water reactor or organic coolant-heavy water reactor
- G21C1/18—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor moderator and coolant being different or separated, e.g. sodium-graphite reactor, sodium-heavy water reactor or organic coolant-heavy water reactor coolant being pressurised
- G21C1/20—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor moderator and coolant being different or separated, e.g. sodium-graphite reactor, sodium-heavy water reactor or organic coolant-heavy water reactor coolant being pressurised moderator being liquid, e.g. pressure-tube reactor
-
- 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)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
FR905573A FR1338441A (fr) | 1962-07-30 | 1962-07-30 | Mode de montage des tubes de force dans un réacteur nucléaire |
Publications (1)
Publication Number | Publication Date |
---|---|
DE1201927B true DE1201927B (de) | 1965-09-30 |
Family
ID=8784252
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
DEG38357A Pending DE1201927B (de) | 1962-07-30 | 1963-07-30 | Leistungsrohr fuer einen Kernreaktor |
Country Status (7)
Country | Link |
---|---|
BE (1) | BE635588A (enrdf_load_stackoverflow) |
DE (1) | DE1201927B (enrdf_load_stackoverflow) |
FR (1) | FR1338441A (enrdf_load_stackoverflow) |
GB (1) | GB1044639A (enrdf_load_stackoverflow) |
LU (1) | LU44023A1 (enrdf_load_stackoverflow) |
NL (1) | NL295992A (enrdf_load_stackoverflow) |
OA (1) | OA00781A (enrdf_load_stackoverflow) |
Families Citing this family (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
LU44938A1 (enrdf_load_stackoverflow) * | 1963-03-13 | 1964-02-04 |
Citations (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE1830496U (de) * | 1960-11-03 | 1961-05-04 | Siemens Ag | Druckrohr mit innenisolierung fuer vorzugsweise schwerwassermoderierte druckroehrenreaktoren. |
FR1269965A (fr) * | 1957-01-04 | 1961-08-18 | Atomic Energy Authority Uk | Réacteur nucléaire |
FR1281779A (fr) * | 1960-03-03 | 1962-01-12 | Atomic Energy Authority Uk | Réacteurs nucléaires |
-
0
- BE BE635588D patent/BE635588A/xx unknown
- NL NL295992D patent/NL295992A/xx unknown
-
1962
- 1962-07-30 FR FR905573A patent/FR1338441A/fr not_active Expired
-
1963
- 1963-07-08 LU LU44023D patent/LU44023A1/xx unknown
- 1963-07-30 GB GB30207/63A patent/GB1044639A/en not_active Expired
- 1963-07-30 DE DEG38357A patent/DE1201927B/de active Pending
-
1964
- 1964-12-15 OA OA50853A patent/OA00781A/xx unknown
Patent Citations (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
FR1269965A (fr) * | 1957-01-04 | 1961-08-18 | Atomic Energy Authority Uk | Réacteur nucléaire |
FR1281779A (fr) * | 1960-03-03 | 1962-01-12 | Atomic Energy Authority Uk | Réacteurs nucléaires |
DE1830496U (de) * | 1960-11-03 | 1961-05-04 | Siemens Ag | Druckrohr mit innenisolierung fuer vorzugsweise schwerwassermoderierte druckroehrenreaktoren. |
Also Published As
Publication number | Publication date |
---|---|
BE635588A (enrdf_load_stackoverflow) | 1900-01-01 |
OA00781A (fr) | 1967-11-15 |
FR1338441A (fr) | 1963-09-27 |
GB1044639A (en) | 1966-10-05 |
LU44023A1 (enrdf_load_stackoverflow) | 1963-09-09 |
NL295992A (enrdf_load_stackoverflow) | 1900-01-01 |
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