JPH0556832B2 - - Google Patents
Info
- Publication number
- JPH0556832B2 JPH0556832B2 JP60272354A JP27235485A JPH0556832B2 JP H0556832 B2 JPH0556832 B2 JP H0556832B2 JP 60272354 A JP60272354 A JP 60272354A JP 27235485 A JP27235485 A JP 27235485A JP H0556832 B2 JPH0556832 B2 JP H0556832B2
- Authority
- JP
- Japan
- Prior art keywords
- residual heat
- nuclear reactor
- pressure vessel
- temperature gas
- steam generator
- 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 - Lifetime
Links
- 239000007789 gas Substances 0.000 claims description 95
- 229910000831 Steel Inorganic materials 0.000 claims description 36
- 239000010959 steel Substances 0.000 claims description 36
- 238000001816 cooling Methods 0.000 claims description 9
- 239000000112 cooling gas Substances 0.000 claims description 9
- 239000000446 fuel Substances 0.000 claims description 7
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 7
- 238000009434 installation Methods 0.000 claims description 6
- 238000004891 communication Methods 0.000 claims description 4
- 239000000498 cooling water Substances 0.000 claims description 4
- 238000002955 isolation Methods 0.000 claims description 2
- 230000005855 radiation Effects 0.000 claims description 2
- 230000001419 dependent effect Effects 0.000 claims 1
- 239000003621 irrigation water Substances 0.000 claims 1
- 238000000605 extraction Methods 0.000 description 11
- 239000001307 helium Substances 0.000 description 7
- 229910052734 helium Inorganic materials 0.000 description 7
- SWQJXJOGLNCZEY-UHFFFAOYSA-N helium atom Chemical compound [He] SWQJXJOGLNCZEY-UHFFFAOYSA-N 0.000 description 7
- 238000010521 absorption reaction Methods 0.000 description 3
- 230000007257 malfunction Effects 0.000 description 3
- 238000005192 partition Methods 0.000 description 3
- 238000013461 design Methods 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- 238000000034 method Methods 0.000 description 2
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 description 1
- 238000007599 discharging Methods 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 229910002804 graphite Inorganic materials 0.000 description 1
- 239000010439 graphite Substances 0.000 description 1
- 238000003780 insertion Methods 0.000 description 1
- 230000037431 insertion Effects 0.000 description 1
- 238000012544 monitoring process Methods 0.000 description 1
- 238000013022 venting Methods 0.000 description 1
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C1/00—Reactor types
- G21C1/32—Integral reactors, i.e. reactors wherein parts functionally associated with the reactor but not essential to the reaction, e.g. heat exchangers, are disposed inside the enclosure with the core
- G21C1/322—Integral reactors, i.e. reactors wherein parts functionally associated with the reactor but not essential to the reaction, e.g. heat exchangers, are disposed inside the enclosure with the core wherein the heat exchanger is disposed above the core
-
- 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
- G21C1/07—Pebble-bed reactors; Reactors with granular fuel
-
- 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
- G21C15/18—Emergency cooling arrangements; Removing shut-down heat
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D9/00—Arrangements to provide heat for purposes other than conversion into power, e.g. for heating buildings
-
- 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
-
- 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)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Treatment Of Water By Oxidation Or Reduction (AREA)
- Investigating Or Analyzing Materials By The Use Of Magnetic Means (AREA)
Applications Claiming Priority (2)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| DE19843446141 DE3446141A1 (de) | 1984-12-18 | 1984-12-18 | In einem stahldruckbehaelter untergebrachte kernreaktoranlage mit einem gasgekuehlten ht-kleinreaktor |
| DE3446141.8 | 1984-12-18 |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS61148388A JPS61148388A (ja) | 1986-07-07 |
| JPH0556832B2 true JPH0556832B2 (en, 2012) | 1993-08-20 |
Family
ID=6253099
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP60272354A Granted JPS61148388A (ja) | 1984-12-18 | 1985-12-03 | 原子炉装置 |
Country Status (3)
| Country | Link |
|---|---|
| US (1) | US4725400A (en, 2012) |
| JP (1) | JPS61148388A (en, 2012) |
| DE (1) | DE3446141A1 (en, 2012) |
Families Citing this family (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| SE8605418L (sv) * | 1986-12-17 | 1988-06-18 | Asea Atom Ab | Reaktor |
| DE3701604A1 (de) * | 1987-01-21 | 1988-08-04 | Hochtemperatur Reaktorbau Gmbh | Kernkraftwerk mit einem gasgekuehlten hochtemperaturreaktor |
| DE3819485C1 (en) * | 1988-06-08 | 1989-04-27 | Hochtemperatur-Reaktorbau Gmbh, 4600 Dortmund, De | Nuclear reactor installation, comprising a high-temperature small reactor, a helium/helium heat exchanger and a helium/water heat exchanger, and method for its operation |
| DE3822212C1 (en) * | 1988-07-01 | 1989-11-16 | Hochtemperatur-Reaktorbau Gmbh, 4600 Dortmund, De | Nuclear reactor installation consisting of a high-temperature small reactor, a helium/helium heat exchanger and a helium/water heat exchanger |
| ATE514165T1 (de) * | 2004-07-28 | 2011-07-15 | Euratom | Kernreaktor integrierter bauart |
| US8437446B2 (en) | 2008-11-17 | 2013-05-07 | Nuscale Power, Llc | Steam generator flow by-pass system |
| CN111768883B (zh) * | 2020-07-21 | 2025-06-03 | 西安热工研究院有限公司 | 一种高温气冷堆核电站冷试期间一回路舱室加热系统及方法 |
Family Cites Families (12)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| DE716521C (de) * | 1940-03-21 | 1942-01-22 | Ernst Schweflinghaus | Mit einem zwanglaeufig bewegten Luftstrom gekuehlter Oberflaechenkondensator, insbesondere fuer Grosskraftdampfmaschinen |
| NL109065C (en, 2012) * | 1955-11-11 | |||
| DE1934952B2 (de) * | 1969-07-10 | 1971-03-18 | Babcock & Wilcox Ltd | Atomkernreaktoranlage |
| DE2160507C3 (de) * | 1971-12-07 | 1975-04-30 | Kernforschungsanlage Juelich Gmbh, 5170 Juelich | Einrichtung zum Kühlen der Strukturwerkstoffe eines Reaktorkerns und zum Abführen der Nachzerfallswärme |
| DE2346868C2 (de) * | 1973-09-18 | 1984-06-07 | Interatom Internationale Atomreaktorbau Gmbh, 5060 Bergisch Gladbach | Flüssigkeitsgekühlter Kernreaktor mit Schildwand zwischen Kühlmittelsammelraum und Druckbehälterwandung |
| US4322268A (en) * | 1978-04-03 | 1982-03-30 | The United States Of America As Represented By The United States Department Of Energy | Cooling system for a nuclear reactor |
| US4367194A (en) * | 1980-09-22 | 1983-01-04 | The United States Of America As Represented By The United States Department Of Energy | Emergency core cooling system |
| DE3141892C2 (de) * | 1981-10-22 | 1985-10-31 | Hochtemperatur-Reaktorbau GmbH, 4600 Dortmund | Kernreaktoranlage |
| DE3149794C1 (de) * | 1981-12-16 | 1983-06-09 | Kernforschungsanlage Jülich GmbH, 5170 Jülich | Kugelhaufen-Kernreaktor mit kugelfoermigen Brennelementen |
| DE3212266C1 (de) * | 1982-04-02 | 1983-06-01 | Hochtemperatur-Reaktorbau GmbH, 5000 Köln | Kernreaktoranlage |
| DE3345113A1 (de) * | 1983-12-14 | 1985-06-27 | Hochtemperatur-Reaktorbau GmbH, 4600 Dortmund | Kernkraftwerk mit einem ht-kleinreaktor |
| DE3435255A1 (de) * | 1984-09-26 | 1986-04-03 | Hochtemperatur-Reaktorbau GmbH, 4600 Dortmund | Kernreaktoranlage mit einem ht-kleinreaktor mit kugelfoermigen brennelementen |
-
1984
- 1984-12-18 DE DE19843446141 patent/DE3446141A1/de active Granted
-
1985
- 1985-12-03 JP JP60272354A patent/JPS61148388A/ja active Granted
- 1985-12-18 US US06/810,243 patent/US4725400A/en not_active Expired - Fee Related
Also Published As
| Publication number | Publication date |
|---|---|
| JPS61148388A (ja) | 1986-07-07 |
| DE3446141A1 (de) | 1986-06-19 |
| DE3446141C2 (en, 2012) | 1993-02-18 |
| US4725400A (en) | 1988-02-16 |
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